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Sample records for korean standardized nuclear

  1. Summary of component reliability data for probabilistic safety analysis of Korean standard nuclear power plant

    International Nuclear Information System (INIS)

    Choi, S. Y.; Han, S. H.

    2004-01-01

    The reliability data of Korean NPP that reflects the plant specific characteristics is necessary for PSA of Korean nuclear power plants. We have performed a study to develop the component reliability DB and S/W for component reliability analysis. Based on the system, we had have collected the component operation data and failure/repair data during plant operation data to 1998/2000 for YGN 3,4/UCN 3,4 respectively. Recently, we have upgraded the database by collecting additional data by 2002 for Korean standard nuclear power plants and performed component reliability analysis and Bayesian analysis again. In this paper, we supply the summary of component reliability data for probabilistic safety analysis of Korean standard nuclear power plant and describe the plant specific characteristics compared to the generic data

  2. The status of Korean nuclear codes and standards

    International Nuclear Information System (INIS)

    Namha Kim; Jong-Hae Kim

    2005-01-01

    Korea Electric Power Industry Code (KEPIC), a set of integrated standards applicable to the design, construction and operation of electric power facilities including nuclear power plants, has been developed on the basis of referring to the prevailing U.S. codes and standards which had been applied to the electric power facilities in Korea. Being the developing and managing organization of KEPIC, Korea Electric Association (KEA) published its first edition in 1995, the second in 200,0 and is expected to publish the 2005 edition. KEPIC was applied to the construction of Ulchin Nuclear Units 5 and 6 in 1997, and will be applicable to the construction of forthcoming nuclear power plants in Korea. Along with the effectuation of the Agreement on Technical Barriers to Trade (TBT) in 1995, the international trend related to codes and standards is changing rapidly. The KEA is, therefore, making its utmost efforts so as for KEPIC to keep abreast with the changing environment in international arena. KEA notified ISO/IEC Information Centre of its acceptance of the Code of Good Practice in the Agreement on TBT. The 2005 KEPIC edition will be retrofitted according to the ISO/IEC Guide 21- Adoption of International Standards as regional or national standards. KEA's efforts will help KEPIC correspond with international standards such as ISO/IEC standards, and internationally recognized standards such as ASME codes and standards. (authors)

  3. Rhodium self-powered neutron detector's lifetime for korean standard nuclear power plants

    International Nuclear Information System (INIS)

    Yoo, Choon Sung; Kim, Byoung Chul; Park, Jong Ho; Fero, Arnold H.; Anderson, S. L.

    2005-01-01

    A method to estimate the relative sensitivity of a self-powered rhodium detector for an upcoming cycle is developed by combining the rhodium depletion data from a nuclear design with the site measurement data. This method can be used both by nuclear power plant designers and by site staffs of Korean standard nuclear power plants for determining which rhodium detectors should be replaced during overhauls

  4. Mitigating Capability Analysis during LOCA for Korean Standard Nuclear Power Plants in Containment Integrity

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Young; Park, Soo Yong; Kim, D. H.; Song, Y. M. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    The objective of this paper is to establish Containment spray operational technical bases for the typical Korean Standard Nuclear Power plants (Ulchin units 3 and 4) by modeling the plant, and analyzing a loss of coolant accident (LOCA) using the MAAP code. The severe accident phenomena at nuclear power plants have large uncertainties. For the integrity of the reactor vessel and containment safety against severe accidents, it is essential to understand severe accident sequences and to assess the accident progression accurately by computer codes. Furthermore, it is important to attain the capability to analyze a advanced nuclear reactor design for a severe accident prevention and mitigation.

  5. The applicability of ALPHA/PHOENIX/ANC nuclear design code system on Korean standard PWR's

    International Nuclear Information System (INIS)

    Lee, Kookjong; Choi, Kie-Yong; Lee, Hae-Chan; Roh, Eun-Rae

    1996-01-01

    For the Korean Standard Nuclear Power Plant (KSNPP) designed based on Combustion Engineering (CE) System 80, the Westinghouse nuclear design code system ALPHA/PHOENIX/ANC was applied to the follow-up design of initial and reload core of KSNPP. The follow-up design results of Yonggwang Unit 3 Cycle 1, 2 and Yonggwang Unit 4 Cycle 1 have shown good agreements with the measured data. The assemblywise power distributions have shown less than 2% average differences and critical boron concentrations have shown less than 20 ppm differences. All the low power physics test parameters are in good agreement. Consequently, APA design code system can be applied to KNSPP cores. (author)

  6. A basic plan for the environment-friendly aspects of improved Korean standard nuclear power plant

    International Nuclear Information System (INIS)

    Jung, Hoon-Seok; Lee, Yong-Koo; Kim, Kwang-Ho

    2006-01-01

    The Improved Korean Standard Nuclear Power Plant (KSNP+) design has been made possible on the basis of engineering experiences and referring to an in-depth analysis of the design and construction of all the domestic nuclear power plants in operation. The KSNP+ is designed for improved safety, better economics, operability and maintainability by means of advanced technology expecting to demonstrate enhanced performance. The plant also has incorporated several environmentally friendly features through the restoration of excavated areas using an ecological approach, external coloring, figure of turbine generator building and landscaping around nuclear power plant. This is the first time that KOPEC has embarked on inducing environmentally friendly features into the basic plan. This is expected to mitigate the negative perceptions held by the residents in the vicinity of nuclear power plants and will contribute to a new and improved image of nuclear power plants. (authors)

  7. Evaluation of post-LOCA long term cooling performance in Korean standard nuclear power plants

    International Nuclear Information System (INIS)

    Bang, Young Seok; Jung, Jae Won; Seul, Kwang Won; Kim, Hho Jung

    2001-01-01

    The post-LOCA long term cooling (LTC) performance of the Korean Standard Nuclear Power Plant (KSNPP) is analyzed for both small break loss-of-coolant accidents (LOCA) and large break LOCA at cold leg. The RELAP5/MOD3.2.2 beta code is used to calculate the LTC sequences based on the LTC plan of the Korean Standard Nuclear Power Plants (KSNPP). A standard input model is developed such that LOCA and the followed LTC sequence can be calculated in a single run for both small break LOCA and large break LOCA. A spectrum of small break LOCA ranging from 0.02 to 0.5 ft 2 of break area and a double-ended guillotine break are analyzed. Through the code calculations, the thermal-hydraulic behavior and the boron behavior are evaluated and the effect of the important action including the safety injection tank (SIT) isolation and the simultaneous injection in LTC procedure is investigated. As a result, it is found that the sufficient margin is available in avoiding the boron precipitation in the core. It is also found that a further specific condition for the SIT isolation action need to be setup and it is recommended that the early initiation of the simultaneous injection be taken for larger break LTC sequences. (author)

  8. Current status and future prospects of Korean standardized nuclear power plant design

    International Nuclear Information System (INIS)

    Rieh, C.-H.; Park, S.-K.; Lee, B.-R.

    1992-01-01

    The authors reviewed a brief history of Korean nuclear industry since the first Kori-1 plant operation in 1978 with special emphasis on the NSSS and BOP design and engineering, and the design approaches for nuclear power plants in the future. Continued effort to enhance plant economy and operational safety has been made by increasing plant size, and improving safety features, systems and component reliability in various design aspects. Korean nuclear industry is now trying to be one of the major contributors to the world nuclear field in sharing nuclear technology gained from past experience and developed through internation technical cooperation programs

  9. Post-LOCA long term cooling performance in Korean standard nuclear power plants

    International Nuclear Information System (INIS)

    Bang, Young Seok; Jung, Jae Won; Seul, Kwang Won; Kim, Hho Jung

    1999-01-01

    The post-LOCA long term cooling (LTC) performance of the Korean Standard Nuclear Power Plant (KSNPP) is analyzed for both small break LOCA and large break LOCA. The RELAP5/MOD3.2.2 code is used to calculate the LTC sequences based on the LTC plan of the KSNPP. A standard input model is developed such that LOCA and the followed LTC sequence can be calculated in a single run for both small break LOCA and large break LOCA. A spectrum of small break LOCA ranging from 0.02 to 0.5 ft 2 of break area and a double-ended guillotine break are analyzed. Through the code calculations, the thermal-hydraulic behavior and the boron behavior are evaluated and the effect of the important manual action including the safety injection tank isolation in LTC procedure is investigated

  10. Improvement of the nuclear plant analyzer for Korean Standard Nuclear Power Plants

    International Nuclear Information System (INIS)

    Choi, Sung Soo; Han, Byoung Sub; Suh, Jae Seung; Son, Dae Seong

    2005-04-01

    Accurate analysis of the operating characteristics of Nuclear Power Plants provides valuable information for both norman and abnormal operation. The information can be used for the enhancement of plant performance and safety. Usually, such analysis is performed using computer codes used for plant design or simulators. However, their usages are limited because special expertise is required to use the computer codes and simulators are not portable. Therefore, it deemed necessary to develop an NPA which minimizes those limitations and can be used for the analysis and simulation of Nuclear Power Plants. The purpose of this study is to develop a real-time best-estimate NPA for the Korean Nuclear Power Plants(KSNP). The NPA is an interactive, high fidelity engineering simulator. NPA combines the process model simulating the plant behavior with the latest computer technology such as Graphical User Interface(GUI) and simulation executive for enhanced user interface. The process model includes models for a three-dimensional reactor core, the NSSS, secondary system including turbine and feedtrain, safety auxiliary systems, and various control systems. Through the verification and validation of the NPA, it was demonstrated that the NPA can realistically simulate the plant behaviors during transient and accident conditions

  11. North Korean nuclear negotiation drama

    International Nuclear Information System (INIS)

    Kim, Jai Bok

    1995-06-01

    This book reports negotiation on North Korean nuclear among South Korea, North Korea and U. S. It includes an account about international issues on North Korean nuclear activities, a new aspect on the problems of North Korean nuclear, pressure on North Korea and startup for dialogue trying to solve problems by communication, investigation by IAEA, IAEA resolution and high tension on Korean peninsula with North Korean nuclear.

  12. North Korean nuclear negotiation drama

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jai Bok

    1995-06-15

    This book reports negotiation on North Korean nuclear among South Korea, North Korea and U. S. It includes an account about international issues on North Korean nuclear activities, a new aspect on the problems of North Korean nuclear, pressure on North Korea and startup for dialogue trying to solve problems by communication, investigation by IAEA, IAEA resolution and high tension on Korean peninsula with North Korean nuclear.

  13. Reliability study: digital engineered safety feature actuation system of Korean Standard Nuclear Power Plant

    International Nuclear Information System (INIS)

    Sudarno; Kang, H. G.; Jang, S. C.; Eom, H. S.; Ha, J. J.

    2003-04-01

    The usage of digital Instrumentation and Control (I and C) in a nuclear power plant becomes more extensive, including safety related systems. The PSA application of these new designs are very important in order to evaluate their reliability. In particular, Korean Standard Nuclear Power Plants (KSNPPs), typically Ulchin 5 and 6 (UCN 5 and 6) reactor units, adopted the digital safety-critical systems such as Digital Plant Protection System (DPPS) and Digital Engineered Safety Feature Actuation System (DESFAS). In this research, we developed fault tree models for assessing the unavailability of the DESFAS functions. We also performed an analysis of the quantification results. The unavailability results of different DESFAS functions showed that their values are comprised from 5.461E-5 to 3.14E-4. The system unavailability of DESFAS AFAS-1 is estimated as 5.461E-5, which is about 27% less than that of analog system if we consider the difference of human failure probability estimation between both analyses. The results of this study could be utilized in risk-effect analysis of KSNPP. We expect that the safety analysis result will contribute to design feedback

  14. Introduction of virtual detectors for core monitoring system of korean standard nuclear power plant

    International Nuclear Information System (INIS)

    Eun, Ki Lee.; Yong, Hee Kim.; Jybe, Ho Cha.; Moon, Ghu Park.

    2000-01-01

    A novel algorithm known as the virtual detector method (VDM) is introduced to reconstruct the axial power shape (APS) for the on-line core monitoring system of the Korean Standard Nuclear Power Plant (KSNP). A pure statistical method (SM) is also introduced and the results are compared with the currently implemented five-mode Fourier fitting method (FFM). VDM adopts nine virtual detector informations coupled with a regression model based on the Alternating Conditional Expectation (ACE) algorithm. VDM uses Fourier fitting with the information of nine virtual detectors expanded from the currently implemented FFM, which uses five-level detector information. By introducing virtual detectors, we can increase the number of axial detectors, and thus expect the computational errors of APS to be reduced. The two methods (SM and VDM) are applied to in-core mapping data from six cycles of Yong Gwang nuclear power plant Units 3 and 4. For ∼ 3500 cases of APSs extracted from a cycle of operation which is simulated by a three-dimensional nodal code, the accuracy of the three methods (SM, VDM, FFM) is compared. The average root mean square (RMS) error and average of axial peaking error of SM and VDM resulted in reduction of more than 50 % and 70 %, respectively, relative to FFM. VDM and SM also show more realistic axial profiles and predict more accurate axial peaking than FFM. These improvements can contribute to a larger thermal margin. SM shows the most accurate results for all cases. VDM can almost obtain the same results as SM, and using far fewer computation steps. VDM can be a useful tool for precisely reconstructing axial power shapes in a core monitoring system. (authors)

  15. Development of the nuclear plant analyzer for Korean standard Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Shin Hwan; Kim, Hyeong Heon; Song, In Ho; Hong, Eon Yeong; Oh, Yeong Taek [Korea Power Engineering Company Inc., Yongin (Korea, Republic of)

    2000-12-15

    The purpose of this study is to develop an NPA for the Ulchin Nuclear Power Plant Unit 3 and 4, the first KSNP type plant. In this study, the process model simulating the overall plant systems, GUI and simulation executive which provide the functions of an engineering simulator were developed, and the NPA was completed by integrating them. The contents and the scope of this study are as follows : main feedwater system, auxiliary feedwater system, Chemical and Volume Control System(CVCS), Safety Injection System(SIS), Shutdown Cooling System(SCS), electric power supply system, Core Protection Calculator(CPC), various plant control system, development of the graphics screens for each system, real-time simulation, simulation control for the enhancement of functional capabilities, user friendly GUI, collection of the design and operating data, establishment of the NPA database, integration of the GUI and simulation control program with process model, collection of the data for the verification and validation of the developed NPA, collection of the plant test data, collection and review of the results of other computer codes, verification of the simulation accuracy by comparing the NPA results with the actual plant data, validation of the simulation capability of the NPA, comparison against available data from other analysis suing different computer codes.

  16. Single failure effects of reactor coolant system large bore hydraulic snubbers for Korean Standard Nuclear Power Plant

    International Nuclear Information System (INIS)

    Choi, T.S.; Park, S.H.; Sung, K.K.; Kim, T.W.; Jheon, J.H.

    1996-01-01

    A potential snubber single failure is one of the safety significances identified in General Safety Issue 113 for Large Bore Hydraulic Snubber (LBHS) dynamic qualification. This paper investigates dynamic structural effects of single failures of the steam generator and reactor coolant pump snubbers in Korean Standard Nuclear Power Plant by performing the time history dynamic analyses for the reactor coolant system under seismic and postulated pipe break events. The seismic input motions considered are the synthesized ground time histories conforming to SRP 3.7.1, and he postulated pipe break input loadings result from steam generator main seam line and feedwater line pipe breaks which govern pipe breaks remaining after applying LBB to the main coolant line and primary side ranch lines equal to and greater than 12 inch nominal pipe size

  17. Development of new NSSS thermal-hydraulic model for Korean standard nuclear power plant(UCN-3/4) simulator

    International Nuclear Information System (INIS)

    Kim, Kyung Doo; Jeong, Jae Jun

    2001-09-01

    The NSSS thermal-hydraulic programs installed in the domestic full-scope power plant simulators were provided in early 1980s by foreign vendors. Because of limited computational capability at that time, they usually adopt very simplified physical models for a real-time simulation of NSSS thermal-hydraulic phenomena, which entails inaccurate results and the possibility of so-called 'negative training', especially for complicated two-phase flows in the reactor coolant system. To resolve the problem, we developed a realistic NSSS T/H program (named 'ARTS-UCN' code) for the improvement of the Korean Standard Nuclear Power Plant full-scope simulator. ARTS Code, developed as an NSSS T/H model for the KNPEC no. 2 simulator using the RETRAN03 code, was selected as a reference code for ARTS-UCN code development. For the development of ARTS, the followings have been performed: - Improvement of the robustness of RETRAN - Improvement of the real-time simulation capability of RETRAN - Optimum input data generation for the NSSS simulation - New model development that cannot be efficiently modeled by RETRAN - Assessment of the ARTS code. The systematic assessment of ARTS has been conducted in both personal computers (Windows 98, Visual fortran) and the simulator development environment (Windows NT, GSE simulator development tool). The results were resonable in terms of accuracy, real-time simulation and robustness

  18. The North Korean nuclear dilemma

    International Nuclear Information System (INIS)

    Hecker, Siegfried S.

    2004-01-01

    The current nuclear crisis, the second one in ten years, erupted when North Korea expelled international nuclear inspectors in December 2002, then withdrew from the Nuclear Nonproliferation Treaty (NPT), and claimed to be building more nuclear weapons with the plutonium extracted from the spent fuel rods heretofore stored under international inspection. These actions were triggered by a disagreement over U.S. assertions that North Korea had violated the Agreed Framework (which froze the plutonium path to nuclear weapons to end the first crisis in 1994) by clandestinely developing uranium enrichment capabilities providing an alternative path to nuclear weapons. With Stanford University Professor John Lewis and three other Americans, I was allowed to visit the Yongbyon Nuclear Center on Jan. 8, 2004. We toured the 5 MWe reactor, the 50 MWe reactor construction site, the spent fuel pool storage building, and the radiochemical laboratory. We concluded that North Korea has restarted its 5 MWe reactor (which produces roughly 6 kg of plutonium annually), it removed the 8000 spent fuel rods that were previously stored under IAEA safeguards from the spent fuel pool, and that it most likely extracted the 25 to 30 kg of plutonium contained in these fuel rods. Although North Korean officials showed us what they claimed was their plutonium metal product from this reprocessing campaign, we were not able to conclude definitively that it was in fact plutonium metal and that it came from the most recent reprocessing campaign. Nevertheless, our North Korean hosts demonstrated that they had the capability, the facility and requisite capacity, and the technical expertise to produce plutonium metal. On the basis of our visit, we were not able to address the issue of whether or not North Korea had a 'deterrent' as claimed - that is, we were not able to conclude that North Korea can build a nuclear device and that it can integrate nuclear devices into suitable delivery systems. However

  19. The Korean nuclear ODA policy development

    International Nuclear Information System (INIS)

    Lee, Seung Hyun; Min, Kim Yoo; Park, Young Il

    2012-01-01

    Korean nuclear Official Development Assistance (ODA) is established with support from institutes such as the Korea International Cooperation Agency (KOICA) and the Korea Atomic Energy Research Institute (KAERI). KOICA's grant aid mainly made through the activities including IAEA's training program, and KAERI currently runs the inter-regional education and training cooperation called Asian Network for Education in Nuclear Technology(ANENT) which aimed to achieve the goal of encouraging web based education training network via cooperation with IAEA. Yet now these programs are focusing more on assisting nuclear infrastructure rather than highlighting nuclear education and training. This paper aims to, first, do a self-evaluation about the Korean ODA policy; second, to study the transition of the international nuclear atmosphere; and third, by apprehending the trend of the subjects of Korean nuclear ODA policy, to discuss the overall appropriate trajectory of Korean nuclear ODA

  20. Nuclear standards

    International Nuclear Information System (INIS)

    Fichtner, N.; Becker, K.; Bashir, M.

    1981-01-01

    This compilation of all nuclear standards available to the authors by mid 1980 represents the third, carefully revised edition of a catalogue which was first published in 1975 as EUR 5362. In this third edition several changes have been made. The title has been condensed. The information has again been carefully up-dated, covering all changes regarding status, withdrawal of old standards, new projects, amendments, revisions, splitting of standards into several parts, combination of several standards into one, etc., as available to the authors by mid 1980. The speed with which information travels varies and requires in many cases rather tedious and cumbersome inquiries. Also, the classification scheme has been revised with the goal of better adjustment to changing situations and priorities. Whenever it turned out to be difficult to attribute a standard to a single subject category, multiple listings in all relevant categories have been made. As in previous editions, within the subcategories the standards are arranged by organization (in Categorie 2.1 by country) alphabetically and in ascending numerical order. It covers all relevant areas of power reactors, the fuel cycle, radiation protection, etc., from the basic laws and governmental regulations, regulatory guides, etc., all the way to voluntary industrial standards and codes of pratice. (orig./HP)

  1. Korean initiatives on nuclear knowledge management

    International Nuclear Information System (INIS)

    Chung, B.-J.; Kim, W.-G.

    2006-01-01

    Korean atomic energy activities have been the vigorous and ever expanding in the peaceful use of atomic energy. However for the last ten-year period, the new recruitments have been drastically reduced. The paper presents the nuclear manpower status in each nuclear related institute, which was surveyed in 2002. The ageing problem appears but is not very serious as a whole. The research institutes show more serious ageing problems compared to the industries. The paper also summarises the initiatives taken by Korean institutes related to the nuclear knowledge management activities with focus on the NtUss (Nuclear Technology Undergraduate Student Society) programme. (author)

  2. Korean standard of postero-anterior cephalography

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Hyung Kyu [College of Dentistry, Seoul National University, Seoul (Korea, Republic of)

    1974-11-15

    The author conducted an experiment using P-A Cephalography of 242 male and female subjects of ages ranging 2-6, 7- 15, and adult group. By means of Nakago's method of measurement, the standard value of Korean was obtained. The results were as follows; 1. In the group of an age, the male value was slightly greater than female value. 2. In each age group the difference between the right and left widths could be recognizable, however, it was not much great. 3. In each group, regardless of sex, the growth relation was clearly distinguishable at PO, ARI, ARE, MG, AG, and CAW. 4. When the standard value of adult Korean was compared with that of Japanese, that of Japanese was great with respect to the width of maxillary portion and that of Korean was great with respect to the width of mandibular portion. 5. Maximum head width of white man was almost similar to that of Korean, however, maxillary alveolar base width of white man was considerably small or the dental arch was narrow.

  3. Improvement of core monitoring code cecor by the virtual segmentation of the self powered neutron detector loaded at Korean Standard Nuclear Plant

    International Nuclear Information System (INIS)

    Choi, T.; Jung, Y.S.

    2006-01-01

    Full text: Full text: Korean Standard Nuclear Plant uses Self Powered Neutron Detectors (SPNDs) to measure the neutron flux in the reactor core. The SPND's height is 40 cm and is located axially at the five different positions and 45 radial places. The design code simulated a reactor core is calculated by segmentation of the core. The segmentation is called as 'node', of which size is normally 20 cm. The axial height of the detector is larger than that of the node, and the larger detector's height maybe product some error on the axially complex shape. The analysis with the detector's signals showed some errors at the non-cosine axial flux shape. In order to reduce the errors for the shape, we tried to divide the detector by introducing the virtual boundary in the detector. Then, each axially 5 detectors had two virtual segmentations respectively and the detector's signal was divided by the inputs. So the more virtual detector's signals were gotten, the more accurate axial shape was produced. The result with virtual segmentations in a detector gave less deviation than the case without virtual segmentation (the current model). After the middle of cycle at the initial core specially, the axial neutron flux shape is changed to the saddle type one. The current model gave some error in Root Mean Square (RMS) between the measured value and the calculated one. The virtual segmentation model gave the better agreement at that time

  4. Present and future of Korean nuclear power

    International Nuclear Information System (INIS)

    Min, K-H

    2014-01-01

    'Full text:' The Korean nuclear power industry has devoted itself to technological development and self-reliance over the last 30 years since Kori unit 1, the first nuclear power plant commenced its commercial operation in 1978. As a result of such efforts and accumulated experiences, the Korean nuclear power industry has developed the OPR 1000 and APR 1400 units and is almost completing the development of the APR+ as a 1,500MW class reactor with its own technologies of design and manufacturing. Also, the Korean nuclear power industry has been able to build a strong supply chain from engineering, manufacturing, construction, and fuel supply, to operation and maintenance. At present, Korea is operating 23 commercial power reactors with a total installed capacity of 20,716 MW, accounting for 25 percent of the installed capacity and one third of the nation's total electricity generation. Also, the share of nuclear power generation capacity will be 29 percent by 2035 in the Long Term Energy Development Plan and 43 GW of nuclear energy capacity will be needed. Thanks to nuclear power generation as an essential driving force, Korea has been able to supply cheap and stable electricity. However, amid the growing public concerns about nuclear safety after the Fukushima accident, the Korean government and related organizations are exerting its utmost effort in all areas, for example, enhancing nuclear safety and safety culture, carrying out management innovation, and communicating with the public in order to enhance transparency. Also, the Korean government launched the Public Engagement Commission on spent nuclear fuel (SNF) management in 2013, which is tasked to initiate public consultation & discussion and submit recommendation to government after in-depth review and analysis on SNF management options by the end of 2014. Nuclear power has become very essential part of national economy in Korea because Korea has virtually no indigenous energy resources and

  5. Present and future of Korean nuclear power

    Energy Technology Data Exchange (ETDEWEB)

    Min, K-H [Korea Atomic Industrial Forum, Inc., Seoul (Korea, Republic of)

    2014-07-01

    'Full text:' The Korean nuclear power industry has devoted itself to technological development and self-reliance over the last 30 years since Kori unit 1, the first nuclear power plant commenced its commercial operation in 1978. As a result of such efforts and accumulated experiences, the Korean nuclear power industry has developed the OPR 1000 and APR 1400 units and is almost completing the development of the APR+ as a 1,500MW class reactor with its own technologies of design and manufacturing. Also, the Korean nuclear power industry has been able to build a strong supply chain from engineering, manufacturing, construction, and fuel supply, to operation and maintenance. At present, Korea is operating 23 commercial power reactors with a total installed capacity of 20,716 MW, accounting for 25 percent of the installed capacity and one third of the nation's total electricity generation. Also, the share of nuclear power generation capacity will be 29 percent by 2035 in the Long Term Energy Development Plan and 43 GW of nuclear energy capacity will be needed. Thanks to nuclear power generation as an essential driving force, Korea has been able to supply cheap and stable electricity. However, amid the growing public concerns about nuclear safety after the Fukushima accident, the Korean government and related organizations are exerting its utmost effort in all areas, for example, enhancing nuclear safety and safety culture, carrying out management innovation, and communicating with the public in order to enhance transparency. Also, the Korean government launched the Public Engagement Commission on spent nuclear fuel (SNF) management in 2013, which is tasked to initiate public consultation & discussion and submit recommendation to government after in-depth review and analysis on SNF management options by the end of 2014. Nuclear power has become very essential part of national economy in Korea because Korea has virtually no indigenous energy resources and

  6. Contrast of Korean industrial standard and overseas standard

    International Nuclear Information System (INIS)

    Kim, Jong Deuk

    2006-12-01

    This book introduces Korean Industrial Standard and Overseas Standard, which deals with furniture, plasticizers, valcaning agents, gaskets, steel pipes and tubes. It covers wooden furniture for offices, washing dresser, children crib, chairs and desks for students, chairs and desks made from synthetic resins, tricresyl phosphate, dibutyl phthalate, dioctyl phthalate, phtalic acid dieptil, V packing, vulcanization accelerator CBS(CZ), vulcanization accelerator MBT(M), vulcanization accelerator Zn BDC, steel pipe for heating furnace and carbon steel pope for high voltage piping.

  7. The Korean nuclear power program

    International Nuclear Information System (INIS)

    Choi, Chang Tong

    1996-01-01

    Although the world nuclear power industry may appear to be in decline, continued nuclear power demand in Korea indicates future opportunities for growth and prosperity in this country. Korea has one of the world's most vigorous nuclear power programs. Korea has been an active promoter of nuclear power generation since 1978, when the country introduced nuclear power as a source of electricity. Korea now takes pride in the outstanding performance of its nuclear power plants, and has established a grand nuclear power scheme. This paper is aimed at introducing the nuclear power program of Korea, including technological development, international cooperation, and CANDU status in Korea. (author). 2 tabs

  8. The North Korean Nuclear Crisis: Outcome and Resolution

    International Nuclear Information System (INIS)

    Lee, Seung-Keun

    2011-01-01

    This paper focuses on the North Korean nuclear crisis and how to find the best method of dismantling the North's nuclear facilities. From empirical studies of North Korean negotiating behavior, strategy, intentions and future of the regime, North Korea seems unlikely to abandon its nuclear program, if left unconstrained. This paper analyzes North Korean nuclear strategy and discusses problems concerned with the North Korean nuclear issues. It will propose some resolutions for a comprehensive approach in order to find a solution to the North Korean nuclear threat: restarting the six-party talks; preparation of a sophisticated nuclear elimination road-map; encouraging the gradual transformation of North Korea and its integration into the international community. In the long run, when North Korean nuclear strategy is considered, dialogue and engagement combined with international pressure or proper sanctions is needed

  9. Strategy. North-Korean nuclear: endgame?

    International Nuclear Information System (INIS)

    Mirandol, Guylain de

    2017-01-01

    As North Korea performed new ballistic missile tests in February 2017, and thus violated UN resolutions, this article proposes an overview of the evolutions from nuclear sanctions to economic sanctions. Initially, UN sanctions aimed at struggling against nuclear programmes and proliferation through embargo on arms and materials. After a nuclear test in 2016, South Korea withdrew from a North Korean industrial complex. International sanctions now aim at economically isolating North Korea, at increasing its trade deficit, and at reducing the sending of currencies by North-Korean expatriates. The author notices that these sanctions do not alter manufacturing activities, and that North Korea thus keeps on developing and being integrated into the international division of labour. The last part briefly discusses how North Korea could be able to get around sanctions

  10. Nuclear standardization development study

    International Nuclear Information System (INIS)

    Pan Jianjun

    2010-01-01

    Nuclear industry is the important part of national security and national economic development is key area of national new energy supported by government. nuclear standardization is the important force for nuclear industry development, is the fundamental guarantee of nuclear safe production, is the valuable means of China's nuclear industry technology to the world market. Now nuclear standardization faces to the new development opportunity, nuclear standardization should implement strategy in standard system building, foreign standard research, company standard building, and talented people building to meet the requirement of nuclear industry development. (author)

  11. A Nuclear Dilemma--Korean War Deja Vu

    Science.gov (United States)

    2006-03-08

    USAWC STRATEGY RESEARCH PROJECT A NUCLEAR DILEMMA—KOREAN WAR DEJA VU by Lieutenant Colonel Trent A. Pickering United States Air Force Colonel William...Lieutenant Colonel Trent A. Pickering TITLE: A Nuclear Dilemma—Korean War Deja Vu FORMAT: Strategy Research Project DATE: 8 March 2006 WORD COUNT: 19,270...1. REPORT DATE 15 MAR 2006 2. REPORT TYPE 3. DATES COVERED 00-00-2005 to 00-00-2006 4. TITLE AND SUBTITLE Nuclear Dilemma--Korean War Deja

  12. Korean nuclear reactor strategy for the early 21st century

    International Nuclear Information System (INIS)

    Lee, Byong Whi; Shin, Young Kyun

    1991-01-01

    The system analysis for Korean nuclear power reactor option is made on the basis of reliability, cost minimization, finite uranium resource availability and nuclear engineering manpower supply constraints. The reference reactor scenarios are developed considering the future electricity demand, nuclear share, current nuclear power plant standardization program and manufacturing capacity. The levelized power generation cost, uranium requirement and nuclear engineering professionals demand are estimated for each reference reactor scenarios and nuclear fuel cycle options from the year 1990 up to the year 2030. Based on the outcomes of the analysis, uranium resource utilization, reliability and nuclear engineering manpower requirements are sensitive to the nuclear reactor strategy and associated fuel cycle whereas the system cost is not. APWR, CANDU: FBR strategy is to be the best option for Korea. However, APWR, CANDU: Passive Safe Reactor (PSR) vFBR strategy should be also considered as a contingency for growing national concerns on nuclear safety and public acceptance deterioration in the future. FBR development and establishment of related fuel cycle should be started as soon as possible considering the uranium shortage anticipated between 2007 and 2032. It should be noted that the increasing use of nuclear energy to minimize the greenhouse effects in the early 21st century would accelerate the uranium resource depletion. The study also concludes that the current level of nuclear engineering professionals employment is not sufficient until 2010 for the establishment of nuclear infrastructure. (Author)

  13. Nuclear proliferation in Northeast Asia: South Korean perspective

    International Nuclear Information System (INIS)

    Seo-Hang Lee

    1995-01-01

    Under new circumstances, that is after the end of the Cold War, the current security situation in Northeast Asia and Korean peninsula is reviewed. The South Korean Non-proliferation policy and its strong commitment to the NPT is embodied in the following: treaty commitments; government officials' statements; presidential declarations; North/South joint declarations; and domestic laws and regulations.Korea has made efforts towards denuclearisation of Korean peninsula. Its nuclear policy is based on peaceful uses of nuclear energy and on maintaining a strong commitment to the NPT. The ultimate goal of its policy is to deter North Korea from developing nuclear weapons and thus secure a nuclear-free Korean peninsula. This could lay foundation for the ultimate creation of region-wide nuclear-free zone in Northeast Asia

  14. Proceedings of the Korean Society Nuclear Medicine Autumn Meeting 2001

    International Nuclear Information System (INIS)

    2001-01-01

    This proceedings contains articles of 2001 autumn meeting of the Korean Society Nuclear Medicine. It was held on November 16-17, 2001 in Seoul, Korea. This proceedings is comprised of 6 sessions. The subject titles of session are as follows: Cancer, Physics of nuclear medicine, Neurology, Radiopharmacy and biology, Nuclear cardiology, General nuclear medicine. (Yi, J. H.)

  15. Considerations on Cyber Security Assessments of Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Jung-Woon; Song, Jae-Gu; Han, Kyung-Soo; Lee, Cheol Kwon; Kang, Mingyun

    2015-01-01

    Korea Institute of Nuclear Nonproliferation and Control (KINAC) has prepared the regulatory standard RS-015 based on RG 5.71. RS-015 defines the elements of a cyber security program to be established in nuclear facilities and describes the security control items and relevant requirements. Cyber security assessments are important initial activities in a cyber security program for NPPs. Cyber security assessments can be performed in the following key steps: 1) Formation of a cyber security assessment team (CSAT); 2) Identification of critical systems and critical digital assets (CDAs); 3) Plant compliance checks with the security control requirements in RS-015. Through the assessments, the current status of security controls applied to NPPs can be found out. The assessments provide baseline data for remedial activities. Additional analyses with the results from the assessments should be performed before the implementation of remedial security controls. The cyber security team at the Korea Atomic Energy Research Institute (KAERI) has studied how to perform cyber security assessments for NPPs based on the regulatory requirements. Recently, KAERI's cyber security team has performed pilot cyber security assessments of a Korean NPP. Based on this assessment experience, considerations and checkpoints which would be helpful for full-scale cyber security assessments of Korean NPPs and the implementation of remedial security controls are discussed in this paper. Cyber security assessment is one of important and immediate activities for NPP cyber security. The quality of the first assessment will be a barometer for NPP cyber security. Hence cyber security assessments of Korean NPPs should be performed elaborately

  16. Considerations on Cyber Security Assessments of Korean Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung-Woon; Song, Jae-Gu; Han, Kyung-Soo; Lee, Cheol Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kang, Mingyun [E-Gonggam Co. Ltd., Daejeon (Korea, Republic of)

    2015-10-15

    Korea Institute of Nuclear Nonproliferation and Control (KINAC) has prepared the regulatory standard RS-015 based on RG 5.71. RS-015 defines the elements of a cyber security program to be established in nuclear facilities and describes the security control items and relevant requirements. Cyber security assessments are important initial activities in a cyber security program for NPPs. Cyber security assessments can be performed in the following key steps: 1) Formation of a cyber security assessment team (CSAT); 2) Identification of critical systems and critical digital assets (CDAs); 3) Plant compliance checks with the security control requirements in RS-015. Through the assessments, the current status of security controls applied to NPPs can be found out. The assessments provide baseline data for remedial activities. Additional analyses with the results from the assessments should be performed before the implementation of remedial security controls. The cyber security team at the Korea Atomic Energy Research Institute (KAERI) has studied how to perform cyber security assessments for NPPs based on the regulatory requirements. Recently, KAERI's cyber security team has performed pilot cyber security assessments of a Korean NPP. Based on this assessment experience, considerations and checkpoints which would be helpful for full-scale cyber security assessments of Korean NPPs and the implementation of remedial security controls are discussed in this paper. Cyber security assessment is one of important and immediate activities for NPP cyber security. The quality of the first assessment will be a barometer for NPP cyber security. Hence cyber security assessments of Korean NPPs should be performed elaborately.

  17. Proceedings of the Korean Society Nuclear Medicine Autumn Meeting 1998

    International Nuclear Information System (INIS)

    1998-01-01

    This proceedings contains articles of 1998 Autumn meeting of the Korean Society Nuclear Medicine. It was held on November 13-14, 1998 in Seoul, Korea. This proceedings is comprised of 5 sessions. The subject titles of session are as follows: general nuclear medicine, neurology, radiopharmacy and biology, nuclear cardiology, physics and instrumentation. (Yi, J. H.)

  18. Proceedings of the Korean Society Nuclear Medicine Autumn Meeting 1997

    International Nuclear Information System (INIS)

    1997-01-01

    This proceedings contains articles of 1997 autumn meeting of the Korean Society Nuclear Medicine. It was held on November 21, 1997 in Kwangju, Korea. This proceedings is comprised of 5 sessions. The subject titles of session are as follows: general nuclear medicine, neurology, radiopharmacy and biology, nuclear cardiology, physics and instrumentation. (Yi, J. H.)

  19. Proceedings of the Korean Society Nuclear Medicine Autumn Meeting 2002

    International Nuclear Information System (INIS)

    2002-01-01

    This proceedings contains articles of 2002 autumn meeting of the Korean Society Nuclear Medicine. It was held on November 15-16, 2002 in Seoul, Korea. This proceedings is comprised of 5 sessions. The subject titles of session are as follows: Cancer, Physics of nuclear medicine, Neurology, Radiopharmacy and biology, General nuclear medicine. (Yi, J. H.)

  20. Nuclear radiation gauge standard

    International Nuclear Information System (INIS)

    Berry, R.L.

    1977-01-01

    A hydrophobic standard for calibrating nuclear radiation moisture gauges is described, comprising a body of superposed interleaved thin layers of a moderating material containing hydrogen in the molecular structure thereof and of a substantially non-moderating material

  1. Construction Improvement for the Korean Nuclear Program

    International Nuclear Information System (INIS)

    Yang, T. E.

    1992-01-01

    Construction of the nine Nuclear plants requires an enormous financial investment. The decision to build a nuclear unit is based on both economic and resource requirements. Korea has few natural resources to use for power generation so the use of diversified fuel sources is a part of the planning process. Nuclear has historically had economic advantages over the fossil fueled plant, however, this advantage has been reduced. This is mainly due to increasing decommissioning and waste disposal costs plus the financial outlays associated with gaining public acceptance of new nuclear units. One of the principal means to recover the economic advantage of a nuclear plant is to shorten the time needed for construction. Every extra day of construction costs large sums of money in interest and escalation expenses alone. The challenge is to shorten the construction period to the minimum feasible time and thereby reduce the financing costs. The methods that have to be employed to achieve this goal require the total commitment from the management of all entities involved in the program. Through the application of advanced management and construction techniques a new era in the construction of nuclear plants in Korea will occur. This will include changes to the methods used for managing, planning, licensing, designing and constructing the new plants. The ability to meet the aggressive plan for the construction of new nuclear power plants in Korea rests in the hands of the managers of all the parties involved. These men set all the rules by which the new plants will be constructed. It is their responsibility to tackle the current problems and develop the solutions to enable the plan to be realized. The changes suggested within this paper are major, but the potential benefits will allow the Korean Nuclear Industry to advance into the twenty first Century as a leader. The number of fully trained specialists needed to make this happen will not appear overnight. They will have to be

  2. Proceedings of the Korean Society Nuclear Medicine Spring Meeting 2002

    International Nuclear Information System (INIS)

    2002-01-01

    This proceedings contains articles of 2002 Spring meeting of the Korean Society Nuclear Medicine. It was held on May 17, 2002 in Suwon, Korea. This proceedings is comprised of 3 sessions. The subject titles of session are as follows: Gynecological and Colorectal cancer, Lung cancer and Lymphoma, and general nuclear medicine. (Yi, J. H.)

  3. How to realize a nuclear-free Korean peninsula

    International Nuclear Information System (INIS)

    Yun, Duk-min

    1992-01-01

    It is certain that, unless the nuclear issue is solved, there can be no progress in inter-Korean relations. To this end, comprehensive and intrusive mutual inspections of any suspicious sites, as well as IAEA inspections, should certainly be implemented. Once international and bilateral arrangements for nuclear inspection are agreed and implemented to the satisfaction of the parties concerned, this will not only solve the problem of nuclear proliferation, but also lay a firm foundation for greater confidence-building measures on the Korean peninsula. This could also be a valuable example for future arms control in Korea. However, even mutual inspection between the two Koreas cannot necessarily guarantee a nuclear-free Korea. The most effective way to ensure the denuclearization of Korea may be to remove elements that the two Koreas perceive as incentives to go nuclear, in parallel with operating a tight and stable verification regime based on mutual and international inspections. Since the major reasons to go nuclear in Korea are military threats and mutual distrust between the two Koreas, no efforts should be spared to rectify these situations. Therefore, confidence- and security-building measures, including full-scale arms control, must be carried out in order to realize and preserve a nuclear-free Korea. In the long run, the greatest contribution to reducing the threat of nuclear proliferation in the Korean peninsula will be through improving overall relations between South and North Korea

  4. The improvement of nuclear safety regulation : American, European, Japanese, and South Korean experiences

    International Nuclear Information System (INIS)

    Cho, Byung Sun

    2005-01-01

    Key concepts in South Korean nuclear safety regulation are safety and risk. Nuclear regulation in South Korea has required reactor designs and safeguards that reduce the risk of a major accident to less than one in a million reactor-years-a risk supposedly low enough to be acceptable. To data, in South Korean nuclear safety regulation has involved the establishment of many technical standards to enable administration enforcement. In scientific lawsuits in which the legal issue is the validity of specialized technical standards that are used for judge whether a particular nuclear power plant is to be licensed, the concept of uncertainty law is often raised with regard to what extent the examination and judgement by the judicial power affects a discretion made by the administrative office. In other words, the safety standards for nuclear power plants has been adapted as a form of the scientific technical standards widely under the idea of uncertainty law. Thus, the improvement of nuclear safety regulation in South Korea seems to depend on the rational lawmaking and a reasonable, judicial examination of the scientific standards on nuclear safety

  5. Technical standards in nuclear area

    International Nuclear Information System (INIS)

    Grimberg, M.

    1978-01-01

    The technical standardization in nuclear area is discussed. Also, the competence of CNEN in standardization pursuit is analysed. Moreover, the process of working up of technical standards is explained; in addition, some kinds of technical standards are discussed. (author) [pt

  6. An application of the valve-leak monitoring system to the valves for the improved Korean standard nuclear power plant (KSNP+)

    International Nuclear Information System (INIS)

    Byeong-yeol AHN; Dae-sik CHOI; Sang-kook CHUNG

    2006-01-01

    The loss of steam due to valve leakage leads to the inefficiency of power generation at the nuclear power plants. Under the normal conditions of plant operation, it is difficult to detect valve leaks early enough to prevent consequential damages and losses. The capability of timely detection allows the plant adequate time to prepare repair plans, which would ultimately result in efficient power production. Therefore, timing of detection is one of the most important factors in dealing with valve leakage problems. The VLMS has been developed to meet such an industrial demand. It provides early detection of valve leakage by real-time monitoring through the acoustic sensors installed on the inlet and the outlet of the valve. The KSNP+ utilizes the VLMS to enhance the performance and maintenance of major valves at plants. The VLMS will enable the plant to detect the leakage of valve at an early stage. It can reduce the steam losses and save related valve maintenance cost by performing fast diagnosis of valve leakage. (authors)

  7. Study on the Internationalization of Korean Nuclear Journals

    International Nuclear Information System (INIS)

    Chun, Y. C.; Yoo, J. B.

    2006-01-01

    This paper is intended to provide some thoughts for a listing of the Korean nuclear journals in the Science Citation Index(SCI), by an analysis of indicators based on the data gathered from relevant literature : Journal of Korean Nuclear Society(JKNS) and Nuclear Engineering and Technology (NET) as cited in the SCI source journal. The study examines as an indicator the number of papers in the JKNS and NET that have been cited by KAERI researchers in the SCI Source Journal (to the end of August 2006). This paper also gives a review of the statistics provided by the Institute for Scientific Information (ISI), as an authoritative source for an evaluation of a global cataloguing of scientific and technical journals, and suggests a view for a listing of the Korean nuclear journals in the SCI by a review of associated selection criteria and methods. It concludes there is a need to increase the number of citations in the SCI source journals of the NET papers to be published from the most recent previous two years

  8. Korean experiences on nuclear power technology

    International Nuclear Information System (INIS)

    Kim, H.; Yang, H.

    1994-01-01

    This paper describes the outstanding performance of the indigenous development program of nuclear power technology such as the design and fabrication of both CANDU and PWR fuel and in the design and construction of nuclear steam supply system in Korea. The success has been accomplished through the successful technology transfer from foreign suppliers and efficient utilization of R and D manpower in the design and engineering of nuclear power projects. In order to implement the technology transfer successfully, the joint design concept has been introduced along with effective on-the-job training and the transfer of design documents and computer codes. Korea's successful development of nuclear power program has resulted in rapid expansion of nuclear power generation capacity in a short time, and the nuclear power has contributed to the national economy through lowering electricity price by about 50 % as well as stabilizing electricity supply in 1980s. The nuclear power is expected to play a key role in the future electricity supply in Korea. Now Korea is under way of taking a step toward advanced nuclear technology. The national electricity system expansion plan includes 18 more units of NPPs to be constructed by the year 2006. In this circumstance, the country has fixed the national long-term nuclear R and D program (lgg2-2001) to enhance the national capability of nuclear technology. This paper also briefly describes future prospects of nuclear technology development program in Korea

  9. A study on international nuclear organizations and conventions for the globalization of Korean nuclear community

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kwang Seok; Oh, Keun Bae; Lee, Byung Wook; Cho, Il Hoon; Lee, Jae Sung; Choi, Young Rok; Ko, Han Seok; Ham, Chul Hoon; Lee, Byung Woon [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-12-01

    The objective of this study is to analyze the current status of international nuclear organizations and conventions in systems perspective and suggest national strategies for utilizing them for the globalization of Korean nuclear community. This study analyzes the current status of international nuclear organizations such as IAEA(International Atomic Energy Agency) and international nuclear conventions related to nuclear accidents, nuclear liability, physical protection or nuclear safety. Based on the analysis, this study suggests national strategies, in general and specific terms, to utilize international nuclear organizations and conventions for the globalization of Korean nuclear community. Separately from this report this study publishes `IAEA Handbook`, which contains all about IAEA such as statute, membership, organizational structure, main activities, finance and budget, etc.. 9 tabs., 2 figs., 35 refs. (Author).

  10. A study on international nuclear organizations and conventions for the globalization of Korean nuclear community

    International Nuclear Information System (INIS)

    Lee, Kwang Seok; Oh, Keun Bae; Lee, Byung Wook; Cho, Il Hoon; Lee, Jae Sung; Choi, Young Rok; Ko, Han Seok; Ham, Chul Hoon; Lee, Byung Woon

    1995-12-01

    The objective of this study is to analyze the current status of international nuclear organizations and conventions in systems perspective and suggest national strategies for utilizing them for the globalization of Korean nuclear community. This study analyzes the current status of international nuclear organizations such as IAEA(International Atomic Energy Agency) and international nuclear conventions related to nuclear accidents, nuclear liability, physical protection or nuclear safety. Based on the analysis, this study suggests national strategies, in general and specific terms, to utilize international nuclear organizations and conventions for the globalization of Korean nuclear community. Separately from this report this study publishes 'IAEA Handbook', which contains all about IAEA such as statute, membership, organizational structure, main activities, finance and budget, etc.. 9 tabs., 2 figs., 35 refs. (Author)

  11. Korean views on needs for international cooperation in development and development of advanced nuclear power systems

    International Nuclear Information System (INIS)

    Yoon, Young Ku; Lee, Byong Whi; Shim, Chang Saeng.

    1993-01-01

    Korea methodology and experience in international cooperation in the field of construction and operation of nuclear power plants as well as Korean views on development and deployment of advanced nuclear nuclear power systems are presented

  12. Korean nuclear industry hit by corruption

    Science.gov (United States)

    Park, Soo Bin

    2013-12-01

    After a four-month investigation, a court in South Korea has indicted 100 officials and suppliers on corruption charges over bogus safety certifications for parts that were supplied to some of the country's 23 nuclear reactors.

  13. The role of research in nuclear regulation: A Korean perspective

    International Nuclear Information System (INIS)

    Yoon, Won-Hyo

    1997-01-01

    Korea has carried out a very ambitious nuclear power program since the 1970's as part of the nation's industrialization policy. Ever since, Korea has also maintained a strong commitment to nuclear power development as an integral part of the national energy policy which aims at reducing external vulnerability and ensuring against a global fossil fuel shortage. The introduction of nuclear power into Korea has progressed through three stages: the first was a turn-key package supplied by the manufacturer; the second involved a major contractor who was responsible for project management, and design and construction was contracted out, with Korean industry becoming more involved; the third stage has seen Korean industries involved as main contractors based on experience gained from earlier plants. The success of Korea's nuclear power program depends in large part on how to insure safety. Safety has the highest priority in nuclear energy development. Public acceptance has been the most critical problem faced by the nuclear industry in Korea. The public demands the highest level of safety all through the design, construction, and operation of nuclear power plants. Korea has learned that a nuclear plant designed with well addressed safety, implementation of a well grounded QA program during construction, and operated with a proven record of safety, are the only ways to earn public support. Competent and efficient regulation with a strong safety culture and openness in all issues is the most desirable image for regulators to strive for. Korea established a ten year R ampersand D program to obtain self-reliance in nuclear technology and international competitiveness by the early 2000's in 1992. It has actively participated in coordinated research programs in safety issues with bodies including the USNRC, AECB of Canada, IAEA, and OECD/NEA

  14. KOREAN STUDENTS' BEHAVIORAL CHANGE TOWARD NUCLEAR POWER GENERATION THROUGH EDUCATION

    Directory of Open Access Journals (Sweden)

    EUN OK HAN

    2014-10-01

    Full Text Available As a result of conducting a 45 minute-long seminar on the principles, state of use, advantages, and disadvantages of nuclear power generation for Korean elementary, middle, and high school students, the levels of perception including the necessity (p<0.017, safety (p<0.000, information acquisition (p<0.000, and subjective knowledge (p<0.000, objective knowledge (p<0.000, attitude (p<0.000, and behavior (p<0.000 were all significantly higher. This indicates that education can be effective in promoting widespread social acceptance of nuclear power and its continued use. In order to induce behavior change toward positive judgments on nuclear power generation, it is necessary to focus on attitude improvement while providing the information in all areas related to the perception, knowledge, attitude, and behavior. Here, the positive message on the convenience and the safety of nuclear power generation should be highlighted.

  15. Current Status of The Korean Society of Nuclear Medicine

    International Nuclear Information System (INIS)

    Koh, Chang Soon

    1977-01-01

    As the application of nuclear medicine to clinics became generalized and it held an important position, the Korean Society of Nuclear Medicine was founded in 1961, and today it has become known as one of the oldest nuclear medicine societies not only to Asian nations but also to other advanced countries all over the world. Now it has 100 or so regular members composed of students of each medicine filed unlike other medical societies. Only nuclear medicine research workers are eligible for its membership. The Korean Society of Nuclear Medicine holds its regular general meeting and symposium twice per annom respectively in addition to occasional group gatherings and provincial lectures on nuclear medicine. With an eye to exchanging information on symposium, research and know-how, KSNM issued its initial magazine in 1967. Every year two editions are published. Year after year the contents of treatises are getting elevated with researches on each field including the early study on morphology-greatly improved both in quality and quantity. Of late, a minute and fixed quantity of various matters by dynamical research and radioimmunoassay of every kind has become visibly active. In particular, since KSNM, unlike other local societies, keeps close and frequent contact with the nuclear medicine researchers of world-wide fame, monographs by eminent scholars of the world are carried in its magazine now internationally and well received in foreign countries. Now the magazine has been improved to such an extent that foreign authors quote its contents. KSNM invited many a foreign scholar with a view to exchanging the knowledge of nuclear medicine. Sponsored by nuclear energy institute, the nuclear medicine symposium held in Seoul in October of 1966 was a success with Dr. Wagner participating, a great scholar of world wide fame: It was the first international symposium ever held in Korea, and the Korea Japan symposium held in Seoul 1971 was attended by all distinguished nuclear

  16. HRD System and Experience in the Korean Nuclear Industry

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Byoungkook [KHNP Nuclear Power Education Institute, Busan (Korea, Republic of)

    2012-03-15

    Korea began to nurture its nuclear energy pioneers in the 1950s when the government dispatched personnel in research and policy-making areas to foreign institutions. Then in 1959, KAERI was established and now plays a leading role in nuclear technology R and D. In addition, Korea's first research reactor, TRIGA Mark-II, was built and put into operation in 1962. This paved the way for advancements in operation and technical development of nuclear reactors. In turn, these accomplishments led to the birth of Korea's first commercial reactor, Kori Unit 1, in the 1970s, and HRD in the nuclear industry was put on the right track. However, the Korean nuclear industry remained heavily dependent on nuclear exporting countries such as the US, Canada, and France. Already confident in construction, Korea took the lead in building Kori Units 3 and 4 and Ulchin Units 1 and 2 in the 1980s, but the country was still in need of technological self-reliance. In order to achieve this, Korea proactively launched systematic HRD programs and dispatched nuclear professionals to overseas nuclear facilities to secure individuals competent in the areas of NPP operations, plant design, and major equipment manufacturing. Thanks to its diligent endeavors, Korea's nuclear entities established independent nuclear training institutes in the 1990s and began producing a large number of competent personnel. This allowed the country to ensure not only the best operation and maintenance engineers but also the essential nuclear technology required for plant design and equipment manufacturing. Since the beginning of the 21{sup st} century, Korea has been producing its nuclear personnel on its own and exchanging nuclear training instructors and trainees with other organizations in fields where specialized knowledge is needed. Furthermore, Korea is taking comprehensive nuclear HRD measures in response to the rising demand for human resources that result from ongoing construction of NPPs in

  17. HRD System and Experience in the Korean Nuclear Industry

    International Nuclear Information System (INIS)

    Kang, Byoungkook

    2012-01-01

    Korea began to nurture its nuclear energy pioneers in the 1950s when the government dispatched personnel in research and policy-making areas to foreign institutions. Then in 1959, KAERI was established and now plays a leading role in nuclear technology R and D. In addition, Korea's first research reactor, TRIGA Mark-II, was built and put into operation in 1962. This paved the way for advancements in operation and technical development of nuclear reactors. In turn, these accomplishments led to the birth of Korea's first commercial reactor, Kori Unit 1, in the 1970s, and HRD in the nuclear industry was put on the right track. However, the Korean nuclear industry remained heavily dependent on nuclear exporting countries such as the US, Canada, and France. Already confident in construction, Korea took the lead in building Kori Units 3 and 4 and Ulchin Units 1 and 2 in the 1980s, but the country was still in need of technological self-reliance. In order to achieve this, Korea proactively launched systematic HRD programs and dispatched nuclear professionals to overseas nuclear facilities to secure individuals competent in the areas of NPP operations, plant design, and major equipment manufacturing. Thanks to its diligent endeavors, Korea's nuclear entities established independent nuclear training institutes in the 1990s and began producing a large number of competent personnel. This allowed the country to ensure not only the best operation and maintenance engineers but also the essential nuclear technology required for plant design and equipment manufacturing. Since the beginning of the 21 st century, Korea has been producing its nuclear personnel on its own and exchanging nuclear training instructors and trainees with other organizations in fields where specialized knowledge is needed. Furthermore, Korea is taking comprehensive nuclear HRD measures in response to the rising demand for human resources that result from ongoing construction of NPPs in Korea and the UAE

  18. Proceedings of 2nd Korea-China Congress of Nuclear Medicine and the Korean Society Nuclear Medicine Spring Meeting 2000

    International Nuclear Information System (INIS)

    2000-01-01

    This proceedings contains articles of 2nd Korea-China Congress of Nuclear Medicine and 2000 spring meeting of the Korean Society Nuclear Medicine. It was held on May 17-19, 2000 in Seoul, Korean. This proceedings is comprised of 6 sessions. The subject titles of session are as follows: general nuclear medicine, neurology, oncology, radiopharmacy and biology, nuclear cardiology, nuclear cardiology: physics and instrumentation and so on. (Yi, J. H.)

  19. Nuclear Power Infrastructure Development Program: Korean Education Program

    International Nuclear Information System (INIS)

    Choi, Sung Yeol; Hwang, Il Soon; Kim, Si Hwan

    2009-01-01

    Many countries have decided nuclear power for next energy resources as one of the long-term energy supply options. IAEA projected nuclear power expansion up to 2030 reaching between 447 GWe and 691 GWe compared to 370 GWe and 2660 TWh at the end of 2006. Both low and high projection is accompanied with new nuclear power plant constructions respectively 178 and 357, about 11 units per year, and most new construction is in North America, the Far East, Eastern Europe, the Middle East, and Southeast Asia. During the last forty years, thirty three countries have established commercial nuclear power programs but only some of them have developed comprehensive and large scale peaceful nuclear power infrastructure. Although various cooperation and guidance program of nuclear power infrastructure, developing appropriate environment and infrastructure of nuclear power plant is still challenging problems for developing countries launching nuclear power program. With increasing the demand of safety and safeguard from international society, creating appropriate infrastructure becomes essential requirements in national nuclear power program. In the viewpoint of developing countries, without sufficient explanation and proper guidance, infrastructure could be seen only as another barrier in its nuclear power program. The importance of infrastructure development would be obscured by ostensible business and infrastructure program can result in increasing entering barriers to peaceful nuclear power application field without benefits to developing countries and international community. To avoid this situation by providing enough explanation and realistic case example and cooperate with the countries wanting to establish comprehensive nuclear power infrastructure in the peaceful applications, we are creating the education program of infrastructure development with basic guidelines of the IAEA infrastructure series and Korean experiences from least developed country to advanced country

  20. Development of RCM analysis software for Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Ho; Choi, Kwang Hee; Jeong, Hyeong Jong [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1999-12-31

    A software called KEPCO RCM workstation (KRCM) has been developed to optimize the maintenance strategies of Korean nuclear power plants. The program modules of the KRCM were designed in a manner that combines EPRI methodologies and KEPRI analysis technique. The KRCM is being applied to the three pilot system, chemical and volume control system, main steam system, and compressed air system of Yonggwang Units 1 and 2. In addition, the KRCM can be utilized as a tool to meet a part of the requirements of maintenance rule (MR) imposed by U.S. NRC. 3 refs., 4 figs. (Author)

  1. Development of RCM analysis software for Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Ho; Choi, Kwang Hee; Jeong, Hyeong Jong [Korea Electric Power Research Institute, Taejon (Korea, Republic of)

    1998-12-31

    A software called KEPCO RCM workstation (KRCM) has been developed to optimize the maintenance strategies of Korean nuclear power plants. The program modules of the KRCM were designed in a manner that combines EPRI methodologies and KEPRI analysis technique. The KRCM is being applied to the three pilot system, chemical and volume control system, main steam system, and compressed air system of Yonggwang Units 1 and 2. In addition, the KRCM can be utilized as a tool to meet a part of the requirements of maintenance rule (MR) imposed by U.S. NRC. 3 refs., 4 figs. (Author)

  2. The Impact of the North Korean Nuclear Crisis on Northeast Asia

    National Research Council Canada - National Science Library

    Han, Jonghun

    2007-01-01

    The DPRK's nuclear issue is difficult to be managed in a peaceful way because of the negative aspects of nuclear proliferation, unacceptable not only on the Korean Peninsula but also in the international community. North Korea, the U.S...

  3. Gap study on technical standards and quality assurance between ITER and Korean regulation

    International Nuclear Information System (INIS)

    Kang, Myoung-suk; Lee, Sangil; Lee, Hyoen Gon; Heo, Gyunyoung

    2016-01-01

    Highlights: • This paper is to secure knowledge and expand domestic specialists for license and regulation of future fusion facilities including K-DEMO. - Abstract: Currently, Korea Domestic Agency (KODA) for the International Thermonuclear Experimental Reactor (ITER) project or the ITER Korea has been conducting follow-up surveys and development researches for the core technologies of its non-procurement items. This eventually aims to secure implicit as well as explicit knowledge and expand domestic specialists for future fusion facilities including K-DEMO. As a part of the project, the comparative analysis and gap study of technical standards and Quality Assurance (QA) system between ITER and Korean nuclear facilities are being performed. The goal of this study is to present a roadmap re-systematizing current safety-related standards for the fission-based facilities into fusion-based facilities in Republic of Korea. The research is considering two different tracks. First one is to secure the state-of-the-art of the fusion technical standards continually updated. For its investigation, we organized the Korean fusion safety advisory group that consists of experts from institutes, industries, and universities. The latest information of technical standards have been gathered and updated from each area of expert in periodic manner. The information is classified into Product Breakdown Structure (PBS) including safety classification, major safety issues, analysis computer codes, etc. This task will be re-organized this year such that the technical standards for procurement as well as non-procurement items can be accumulated in systematic and sustainable manner. Second one, called “Gap Study,” is to compare the requirements for domestic nuclear facilities and the results from the first track on the basis of experts’ opinion from the national and private sectors and to recommend the approaches to overcome technical and administrative barriers. The result is

  4. Gap study on technical standards and quality assurance between ITER and Korean regulation

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Myoung-suk [Kyung Hee University, Yongin-si 446-701, Gyeonggi-do (Korea, Republic of); Lee, Sangil; Lee, Hyoen Gon [National Fusion Research Institute, Daejeon-si 305-333 (Korea, Republic of); Heo, Gyunyoung, E-mail: gheo@khu.ac.kr [Kyung Hee University, Yongin-si 446-701, Gyeonggi-do (Korea, Republic of)

    2016-11-01

    Highlights: • This paper is to secure knowledge and expand domestic specialists for license and regulation of future fusion facilities including K-DEMO. - Abstract: Currently, Korea Domestic Agency (KODA) for the International Thermonuclear Experimental Reactor (ITER) project or the ITER Korea has been conducting follow-up surveys and development researches for the core technologies of its non-procurement items. This eventually aims to secure implicit as well as explicit knowledge and expand domestic specialists for future fusion facilities including K-DEMO. As a part of the project, the comparative analysis and gap study of technical standards and Quality Assurance (QA) system between ITER and Korean nuclear facilities are being performed. The goal of this study is to present a roadmap re-systematizing current safety-related standards for the fission-based facilities into fusion-based facilities in Republic of Korea. The research is considering two different tracks. First one is to secure the state-of-the-art of the fusion technical standards continually updated. For its investigation, we organized the Korean fusion safety advisory group that consists of experts from institutes, industries, and universities. The latest information of technical standards have been gathered and updated from each area of expert in periodic manner. The information is classified into Product Breakdown Structure (PBS) including safety classification, major safety issues, analysis computer codes, etc. This task will be re-organized this year such that the technical standards for procurement as well as non-procurement items can be accumulated in systematic and sustainable manner. Second one, called “Gap Study,” is to compare the requirements for domestic nuclear facilities and the results from the first track on the basis of experts’ opinion from the national and private sectors and to recommend the approaches to overcome technical and administrative barriers. The result is

  5. Failure trend analysis for safety related components of Korean standard NPPs

    International Nuclear Information System (INIS)

    Choi, Sun Yeong; Han, Sang Hoon

    2005-01-01

    The component reliability data of Korean NPP that reflects the plant specific characteristics is required necessarily for PSA of Korean nuclear power plants. We have performed a project to develop the component reliability database (KIND, Korea Integrated Nuclear Reliability Database) and S/W for database management and component reliability analysis. Based on the system, we have collected the component operation data and failure/repair data during from plant operation date to 2002 for YGN 3, 4 and UCN 3, 4 plants. Recently, we provided the component failure rate data for UCN 3, 4 standard PSA model from the KIND. We evaluated the components that have high-ranking failure rates with the component reliability data from plant operation date to 1998 and 2000 for YGN 3,4 and UCN 3, 4 respectively. We also identified their failure mode that occurred frequently. In this study, we analyze the component failure trend and perform site comparison based on the generic data by using the component reliability data which is extended to 2002 for UCN 3, 4 and YGN 3, 4 respectively. We focus on the major safety related rotating components such as pump, EDG etc

  6. Argentine nuclear energy standardization activities

    International Nuclear Information System (INIS)

    Boero, Norma; Corcuera, Roberto; Palacios, Tulio A.; Hey, Alfredo M.; Berte, G.; Trama, L.

    2004-01-01

    The International Organization for Standardization (ISO) has more than 200 Technical Committees that develop technical standards. During April 2004 took place in Buenos Aires the 14th Plenary of the ISO/TC 85 Nuclear Energy Committee. During this Plenary issues as Nuclear Terminology, Radiation Protection, Nuclear Fuels, Nuclear Reactors and Irradiation Dosimetry was dealt with. 105 International delegates and 45 National delegates (belonging to CNEA, ARN, NASA, INVAP, CONUAR, IONICS and other organizations) attended the meetings. During this meeting ISO/TC 85 changed its scope; the new scope of the Committee is 'Standardization in the fields of peaceful applications of nuclear energy and of the protection of individuals against all sources of ionizing radiations'. This work summarizes the most important advances and resolutions about the development of standards taken during this meeting as well as the main conclusions. (author) [es

  7. Status of the Korean nuclear hydrogen production project

    International Nuclear Information System (INIS)

    Jonghwa, Chang; Won-Jae, Lee

    2010-01-01

    The rapid climate changes and the heavy reliance on imported fuel in Korea have motivated interest in the hydrogen economy. The Korean government has set up a long-term vision for transition to the hydrogen economy. To meet the expected demand of hydrogen as a fuel, hydrogen production using nuclear energy was also discussed. Recently the Korean Atomic Energy Committee has approved nuclear hydrogen production development and demonstration which will lead to commercialisation in late 2030's. An extensive research and development programme for the production of hydrogen using nuclear power has been underway since 2004 in Korea. During the first three years, a technological area was identified for the economic and efficient production of hydrogen using a VHTR. A pre-conceptual design of the commercial nuclear hydrogen production plant was also performed. As a result, the key technology area in the core design, the hydrogen production process, the coupling between reactor and chemical side, and the coated fuel were identified. During last three years, research activities have been focused on the key technology areas. A nuclear hydrogen production demonstration plant (NHDD) consisting of a 200 MWth capacity VHTR and five trains of water-splitting plants was proposed for demonstration of the performance and the economics of nuclear hydrogen. The computer tools for the VHTR and the water-splitting process were created and validated to some extent. The TRISO-coated particle fuel was fabricated and qualified. The properties of high temperature materials, including nuclear graphite, were studied. The sulphur-iodine thermochemical process was proved on a 3 litre/ hour scale. A small gas loop with practical pressure and temperature with the secondary sulphur acid loop was successfully built and commissioned. The results of the first phase research increased the confidence in the nuclear hydrogen technology. From 2009, the government decided to support further key technology

  8. Review of the Korean SSAC According to Changes in the Nuclear Environment

    International Nuclear Information System (INIS)

    Kim, Min Su; Yoon, Wan Ki; Choe, Kwan Kyoo; Jo, Seong Youn; Park, Jae Bum

    2005-01-01

    Korea has been maintaining efficient and systematic State System for Accounting and Control of nuclear materials (SSAC) for elevation of our nuclear transparency and reliability to international society. So far, Korean SSAC had been considered as a good example of SSAC together with Euratom, Japan, ABACC. But, owing to changing environment such as a series trial due to the KAERI's past nuclear material experiments, strengthened international nonproliferation scheme, advent of integrated safeguards and technology development in nuclear fields, voices of demand for changes in Korean SSAC are being brought up. Therefore, this study grasped and analyzed international nuclear environment and direction of changes in nuclear control regime, besides re-examine the roles of Korean SSAC and proposed the direction where Korean SSAC should be shifted

  9. Past and future of the Korean national nuclear energy development program

    International Nuclear Information System (INIS)

    Moon, Joo Hyun

    2012-01-01

    The Korean government promulgated the 4th Comprehensive Nuclear Energy Promotion Plan (CNEPP) in November 2011, which included the objectives and strategies with the overriding priority that the Korean government and nuclear institutes should carry forward to achieve over next 5 years. Since 1997, when the first CNEPP was promulgated, the Korean government has modified and supplemented the CNEPP every 5 years based on an analysis of the outcomes of the previous CNEPP as well as the outlook on the future nuclear energy uses and developments in domestic and foreign countries. This paper reviews the history of the CNEPP and gives a general idea of the 4th CNEPP. (orig.)

  10. Seismological analysis of the fourth North Korean nuclear test

    Science.gov (United States)

    Hartmann, Gernot; Gestermann, Nicolai; Ceranna, Lars

    2016-04-01

    The Democratic People's Republic of Korea has conducted its fourth underground nuclear explosions on 06.01.2016 at 01:30 (UTC). The explosion was clearly detected and located by the seismic network of the International Monitoring System (IMS) of the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Additional seismic stations of international earthquake monitoring networks at regional distances, which are not part of the IMS, are used to precisely estimate the epicenter of the event in the North Hamgyong province (41.38°N / 129.05°E). It is located in the area of the North Korean Punggye-ri nuclear test site, where the verified nuclear tests from 2006, 2009, and 2013 were conducted as well. The analysis of the recorded seismic signals provides the evidence, that the event was originated by an explosive source. The amplitudes as well as the spectral characteristics of the signals were examined. Furthermore, the similarity of the signals with those from the three former nuclear tests suggests very similar source type. The seismograms at the 8,200 km distant IMS station GERES in Germany, for example, show the same P phase signal for all four explosions, differing in the amplitude only. The comparison of the measured amplitudes results in the increasing magnitude with the chronology of the explosions from 2006 (mb 4.2), 2009 (mb 4.8) until 2013 (mb 5.1), whereas the explosion in 2016 had approximately the same magnitude as that one three years before. Derived from the magnitude, a yield of 14 kt TNT equivalents was estimated for both explosions in 2013 and 2016; in 2006 and 2009 yields were 0.7 kt and 5.4 kt, respectively. However, a large inherent uncertainty for these values has to be taken into account. The estimation of the absolute yield of the explosions depends very much on the local geological situation and the degree of decoupling of the explosive from the surrounding rock. Due to the missing corresponding information, reliable magnitude-yield estimation for the

  11. ISO standardization in nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Brabec, D [Ustav pro Vyzkum, Vyrobu a Vyuziti Radioisotopu, Prague (Czechoslovakia); Cermak, O [Urad pro Normalizaci a Mereni, Prague (Czechoslovakia)

    1984-10-01

    The activity is described of the technical commission ISO/TC 85 which is currently divided into 4 subcommissions (SC) and 24 working groups. SC 1 ''Terminology, definitions, units, abbreviations'' has one working group. The most important document of this SC is ISO 921-1972 (Dictionary of nuclear technology). SC 2 ''Radiation protection'' has 9 working groups and has processed standards in dosimetry. SC 3 ''Technology of power reactors'' has 6 working groups and its work is related to IAEA activities within the NUSS program. SC 4 ''Technology of nuclear fuels'' has 8 working groups. SC 4 has compiled the basic standards for sealed sources and methods of testing their tightness. The results of the work of this group have been reflected into the standardization work of CMEA. A list is given of published international standards within TC 85.

  12. Korean efforts for education and training network in nuclear technology

    International Nuclear Information System (INIS)

    Han, Kyong-Won; Lee, Eui-Jin

    2007-01-01

    Nuclear energy has been a backbone for Korea's remarkable economic growth, and will continue its essential role with 18 nuclear power plants in operation, 2 more units under construction, 6 more units in planning. Korea is operating its own designed nuclear power plants, such as KSNP, 1400, as well as self-design and operation of 30 MW Hanaro research reactor. Korea makes strong efforts to develop future nuclear technology. They are the System-Integrated Modular Advanced Reactor, SMART, Korea Advanced Liquid Metal reactor, KALIMER, Hydrogen Production reactor, and Proliferation-resistant Nuclear Fuel Cycle. In parallel, Korea is establishing an Advanced Radiation Technology R and D Center and a High Power Proton Accelerator Center. International, next generation nuclear power technologies are being developed through projects such as the IAEA Innovative Nuclear Reactors and Fuel Cycle, INPRO, Generation IV International Forum, GIF, and International thermonuclear Experimental reactor, ITER. In the new millennium, Korea expects that radiation technology combined with bio, nano, and space technology will sustain our civilization. About 21,000 qualified nuclear human resources are engaged in power and non-power fields such as design and manufacturing of equipment, plant operation and maintenance, safety, RI production, R and D, etc. However, it is recognized that the first generation of nuclear work force is getting older and retired, less of our youth are studying nuclear science and engineering. Korean Government has established a promotion program on nuclear human resources development, which is needed until 2010. For the sustainable development of nuclear science and technology, it calls for more qualified human resources. We ought to encourage our youth to become more interested in nuclear studies and careers. Korea is making strong efforts to support nuclear education and training for young generations. It is believed that internationally accepted advanced

  13. Nuclear Control in Korean Peninsula: Status and Prospect

    International Nuclear Information System (INIS)

    Choe, Kwan-Kyoo

    2007-01-01

    This paper is aiming at finding out an authentic meaning of implementation of the IAEA Strengthened Safeguards System (SSS) in South Korea, and also the implementation of the joint agreement in North Korea concluded among the six nations on Feb. 13, 2007. The approach for development of the paper would be limited to the dimension of nuclear control. The actual implementation of the Additional Protocol (AP) and the entry into force of the Integrated Safeguards System in a near future in South Korea have passed a few of technical and diplomatic complications. Specially the past mistakes related to declaration to IAEA made by researchers resulted in a more strengthened transparency policy in South Korea, which was announced as a form of four-point statement reassuring the international community of its commitment to a nuclear-free policy on the Korean peninsula in 2004. North Korea rejected special inspection demanded by IAEA in 1992 related to its initial declaration to apply the IAEA INFCIRC/153 type of safeguards system. The rejection had consisted of the base line of diplomatic conflict between North Korea and international community. However, change of position of North Korea, even being uncertain still as of today, arrived at the joint declaration of '9-19' among 6 nations of Six-Party Talks in 2005, which developed into the conclusion of joint agreement for the implementation of the '9-19' principles on Feb. 13, 2007

  14. Nuclear Data Verification and Standardization

    Energy Technology Data Exchange (ETDEWEB)

    Karam, Lisa R.; Arif, Muhammad; Thompson, Alan K.

    2011-10-01

    The objective of this interagency program is to provide accurate neutron interaction verification and standardization data for the U.S. Department of Energy Division of Nuclear Physics programs which include astrophysics, radioactive beam studies, and heavy-ion reactions. The measurements made in this program are also useful to other programs that indirectly use the unique properties of the neutron for diagnostic and analytical purposes. These include homeland security, personnel health and safety, nuclear waste disposal, treaty verification, national defense, and nuclear based energy production. The work includes the verification of reference standard cross sections and related neutron data employing the unique facilities and capabilities at NIST and other laboratories as required; leadership and participation in international intercomparisons and collaborations; and the preservation of standard reference deposits. An essential element of the program is critical evaluation of neutron interaction data standards including international coordinations. Data testing of critical data for important applications is included. The program is jointly supported by the Department of Energy and the National Institute of Standards and Technology.

  15. Nuclear security standard: Argentina approach

    International Nuclear Information System (INIS)

    Bonet Duran, Stella M.; Rodriguez, Carlos E.; Menossi, Sergio A.; Serdeiro, Nelida H.

    2007-01-01

    Argentina has a comprehensive regulatory system designed to assure the security and safety of radioactive sources, which has been in place for more than fifty years. In 1989 the Radiation Protection and Nuclear Safety branch of the National Atomic Energy Commission created the 'Council of Physical Protection of Nuclear Materials and Installations' (CAPFMIN). This Council published in 1992 a Physical Protection Standard based on a deep and careful analysis of INFCIRC 225/Rev.2 including topics like 'sabotage scenario'. Since then, the world's scenario has changed, and some concepts like 'design basis threat', 'detection, delay and response', 'performance approach and prescriptive approach', have been applied to the design of physical protection systems in facilities other than nuclear installations. In Argentina, radioactive sources are widely used in medical and industrial applications with more than 1,600 facilities controlled by the Nuclear Regulatory Authority (in spanish ARN). During 2005, measures like 'access control', 'timely detection of intruder', 'background checks', and 'security plan', were required by ARN for implementation in facilities with radioactive sources. To 'close the cycle' the next step is to produce a regulatory standard based on the operational experience acquired during 2005. ARN has developed a set of criteria for including them in a new standard on security of radioactive materials. Besides, a specific Regulatory Guide is being prepared to help licensees of facilities in design a security system and to fulfill the 'Design of Security System Questionnaire'. The present paper describes the proposed Standard on Security of Radioactive Sources and the draft of the Nuclear Security Regulatory Guidance, based on our regulatory experience and the latest international recommendations. (author)

  16. Reconstructing the public in old and new governance: a Korean case of nuclear energy policy.

    Science.gov (United States)

    Kim, Hyomin

    2014-04-01

    Korean nuclear energy regulatory policies started to change from earlier exclusively technocratic policies into open dialogues after several anti-nuclear protests in the 1990s. However, technocratic policies still coexist with the new regulatory orientation towards openness, participation and institutional accountability. This paper analyzes Korean nuclear regulatory policies since approximately 2005 as a blend of old and new governance. The aim of the paper is not to decide whether new nuclear governance is deliberative or not by completely reviewing Korean nuclear policies after the 2000s. Instead, it provides an empirical account of how seemingly more participatory processes in decision-making entail new problems while they work with and reproduce social assumptions of different groups of the public.

  17. Register of international standard NP on IT based wireless application in nuclear power plants

    International Nuclear Information System (INIS)

    Koo, I. S.; Hong, S. B.; Cho, I. W.; Choi, Y. S.; Lee, J. C.

    2011-04-01

    DC draft of standard technical report for wireless applications in NPP is developed, which is a Korean IT technologies. Wireless technologies are forwardwd to converging technologies nuclear and IT area. These technologies are supported to reduce vulnerability against cyber attacks and are forwarded to international standards which met with the nuclear environment requirements. DC draft of standard technical report is provided and circulated. Korean experts participate in Plenary meeting for IEC TC45/SC45A and intermediate meeting for IEC SC45A/WGA3 and 9. Korean expert takes the chair of wireless session at ANS winter conference. Visible light communication is experimented for feasibility study on reducing vulnerability against cyber attacks. VLC is capable of robust wireless communication against cyber attacks. This is suggested to describe a method for technical report. Issue DTR for wireless applications in NPP in 2012

  18. ISO standardization in nuclear technology

    Energy Technology Data Exchange (ETDEWEB)

    Brabec, D. (Ustav pro Vyzkum, Vyrobu a Vyuziti Radioisotopu, Prague (Czechoslovakia)); Cermak, O. (Urad pro Normalizaci a Mereni, Prague (Czechoslovakia))

    1984-10-01

    The activity is described of the technical commission ISO/TC 85 which is currently divided into 4 subcommissions (SC) and 24 working groups. SC 1 ''Terminology, definitions, units, abbreviations'' has one working group. The most important document of this SC is ISO 921-1972 (Dictionary of nuclear technology). SC 2 ''Radiation protection'' has 9 working groups and has processed standards in dosimetry. SC 3 ''Technology of power reactors'' has 6 working groups and its work is related to IAEA activities within the NUSS program. SC 4 ''Technology of nuclear fuels'' has 8 working groups. SC 4 has compiled the basic standards for sealed sources and methods of testing their tightness. The results of the work of this group have been reflected into the standardization work of CMEA. A list is given of published international standards within TC 85.

  19. Comparison of the Standards applied to Instrumentation and Control Systems for Nuclear Power Stations in Korea and Russia

    International Nuclear Information System (INIS)

    Park, Joo Hyun; Hwang, In Koo; Lee, Dong Young

    2005-04-01

    This report describes a comparison result of technical standards applied to instrumentation and control systems for nuclear power plants between in Korea and in Russia. Russia also has a state-run organization authorized to conduct approval, cancellation, and audit in use of nuclear facility or equipment. The Russian standards for nuclear instrumentation and control equipment are analogous with the Korean ones in the aspect of basic concepts and principles. However, there are some differences in document structure, design requirements, qualification test items, depth of contents between two standard systems. The biggest deviation exists in the standard documents for seismic qualification and electromagnetic interference qualification. Korean seismic qualification standard utilizing US approach, defines testing and qualification methods specifically and clearly. Russian standards however provide only conceptual definitions and requirements in the seismic related aspects. Therefore, it is conceived that any equipment or system qualified seismically in accordance with Korean standards should additionally provide technical evidence that it is satisfactory with Russian standards as well. In electromagnetic interference qualification, because Russian standard requires more testing items than the current Korean standard, the additional qualification tests are necessary to meet the Russian requirements. However, these additional test items are based on IEC(International Electrotechnical Commission), therefore it is not a problem to perform those tests in a Korean testing facility

  20. Comparison of the Standards applied to Instrumentation and Control Systems for Nuclear Power Stations in Korea and Russia

    Energy Technology Data Exchange (ETDEWEB)

    Park, Joo Hyun; Hwang, In Koo; Lee, Dong Young

    2005-04-15

    This report describes a comparison result of technical standards applied to instrumentation and control systems for nuclear power plants between in Korea and in Russia. Russia also has a state-run organization authorized to conduct approval, cancellation, and audit in use of nuclear facility or equipment. The Russian standards for nuclear instrumentation and control equipment are analogous with the Korean ones in the aspect of basic concepts and principles. However, there are some differences in document structure, design requirements, qualification test items, depth of contents between two standard systems. The biggest deviation exists in the standard documents for seismic qualification and electromagnetic interference qualification. Korean seismic qualification standard utilizing US approach, defines testing and qualification methods specifically and clearly. Russian standards however provide only conceptual definitions and requirements in the seismic related aspects. Therefore, it is conceived that any equipment or system qualified seismically in accordance with Korean standards should additionally provide technical evidence that it is satisfactory with Russian standards as well. In electromagnetic interference qualification, because Russian standard requires more testing items than the current Korean standard, the additional qualification tests are necessary to meet the Russian requirements. However, these additional test items are based on IEC(International Electrotechnical Commission), therefore it is not a problem to perform those tests in a Korean testing facility.

  1. Applicable approach of the wireless technology for Korean nuclear power plants

    International Nuclear Information System (INIS)

    Ko, Do Young; Lee, Soo Ill

    2013-01-01

    Highlights: • To apply wireless technology for Korean NPPs, several stipulations are proposed. • WLAN is proposed as the most appropriate wireless technology for Korean NPPs. • WLAN can be applied to the specific fields except in the control system. • An attitude survey on wireless showed that 94.7% agree with the necessity of wireless. - Abstract: Recently, many nuclear power plants (NPPs) over the world use various types of wireless systems for the advantages. Unfortunately, wireless technologies are not currently installed in any Korean NPPs because it is difficult to solve the negative impact of unexpected outcomes or failures from the influence of the wireless technologies, which is electromagnetic interference and radio-frequency interference (EMI/RFI). Moreover, a lack of desire on the part of Korean nuclear industry to implement it leads to give up benefit from the wireless technologies. To install the wireless technologies with maximum benefit and minimum risk, a systematic approach, which quantify the negative impact and prevent the influence, is essential; therefore, this paper describes an applicable research result on the wireless technology for Korean NPPs based on regulatory guides and current wireless hardware and software technologies. Also, survey on the needs for the wireless technology for Korean nuclear power plants was conducted, because the level of awareness of workers in NPPs regarding wireless technologies is very important issue. In this paper, we propose an applicable system to enhance the applicability for the wireless technology for Korean NPPs. The result based on proposed applicable system shows that wireless local area network (WLAN) is the representative candidate for Korean NPPs, which can be applied to the specific fields of radiation monitoring, voice and data communication, component monitoring and instrumentation, and wireless cameras

  2. Applicable approach of the wireless technology for Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Do Young, E-mail: kodoyoung@khnp.co.kr; Lee, Soo Ill

    2013-12-15

    Highlights: • To apply wireless technology for Korean NPPs, several stipulations are proposed. • WLAN is proposed as the most appropriate wireless technology for Korean NPPs. • WLAN can be applied to the specific fields except in the control system. • An attitude survey on wireless showed that 94.7% agree with the necessity of wireless. - Abstract: Recently, many nuclear power plants (NPPs) over the world use various types of wireless systems for the advantages. Unfortunately, wireless technologies are not currently installed in any Korean NPPs because it is difficult to solve the negative impact of unexpected outcomes or failures from the influence of the wireless technologies, which is electromagnetic interference and radio-frequency interference (EMI/RFI). Moreover, a lack of desire on the part of Korean nuclear industry to implement it leads to give up benefit from the wireless technologies. To install the wireless technologies with maximum benefit and minimum risk, a systematic approach, which quantify the negative impact and prevent the influence, is essential; therefore, this paper describes an applicable research result on the wireless technology for Korean NPPs based on regulatory guides and current wireless hardware and software technologies. Also, survey on the needs for the wireless technology for Korean nuclear power plants was conducted, because the level of awareness of workers in NPPs regarding wireless technologies is very important issue. In this paper, we propose an applicable system to enhance the applicability for the wireless technology for Korean NPPs. The result based on proposed applicable system shows that wireless local area network (WLAN) is the representative candidate for Korean NPPs, which can be applied to the specific fields of radiation monitoring, voice and data communication, component monitoring and instrumentation, and wireless cameras.

  3. Component reliability analysis for development of component reliability DB of Korean standard NPPs

    International Nuclear Information System (INIS)

    Choi, S. Y.; Han, S. H.; Kim, S. H.

    2002-01-01

    The reliability data of Korean NPP that reflects the plant specific characteristics is necessary for PSA and Risk Informed Application. We have performed a project to develop the component reliability DB and calculate the component reliability such as failure rate and unavailability. We have collected the component operation data and failure/repair data of Korean standard NPPs. We have analyzed failure data by developing a data analysis method which incorporates the domestic data situation. And then we have compared the reliability results with the generic data for the foreign NPPs

  4. The role of nuclear energy system for Korean long-term energy supply strategy

    International Nuclear Information System (INIS)

    Chae, K.N.; Lee, D.G.; Lim, C.Y.; Lee, B.W.

    1995-01-01

    The energy supply optimization model MESSAGE-III is improved to evaluate the role of nuclear energy system in Korean long-term energy supply strategy. Emphasis is placed on the potential contribution of nuclear energy in case of environmental constraints and energy resource limitation. The time horizon is 1993-2040. A program to forecast useful energy demand is developed, and optimization is performed from the overall energy system to the nuclear energy system. Reactor and fuel cycle strategy and the expanded utilization options for nuclear energy system are suggested. FBRs, HTGRs and thorium fuel cycle would play key roles in the long run. The most important factors for nuclear energy in Korean energy supply strategy would be the availability of fossil fuels, CO 2 reduction regulation, and the supply capability of nuclear energy. (author)

  5. Design of Korean nuclear reliability data-base network using a two-stage Bayesian concept

    International Nuclear Information System (INIS)

    Kim, T.W.; Jeong, K.S.; Chae, S.K.

    1987-01-01

    In an analysis of probabilistic risk, safety, and reliability of a nuclear power plant, the reliability data base (DB) must be established first. As the importance of the reliability data base increases, event reporting systems such as the US Nuclear Regulatory Commission's Licensee Event Report and the International Atomic Energy Agency's Incident Reporting System have been developed. In Korea, however, the systematic reliability data base is not yet available. Therefore, foreign data bases have been directly quoted in reliability analyses of Korean plants. In order to develop a reliability data base for Korean plants, the problem is which methodology is to be used, and the application limits of the selected method must be solved and clarified. After starting the commercial operation of Korea Nuclear Unit-1 (KNU-1) in 1978, six nuclear power plants have begun operation. Of these, only KNU-3 is a Canada Deuterium Uranium pressurized heavy-water reactor, and the others are all pressurized water reactors. This paper describes the proposed reliability data-base network (KNRDS) for Korean nuclear power plants in the context of two-stage Bayesian (TSB) procedure of Kaplan. It describes the concept of TSB to obtain the Korean-specific plant reliability data base, which is updated with the incorporation of both the reported generic reliability data and the operation experiences of similar plants

  6. Reliability and validity of the Korean standard pattern identification for stroke (K-SPI-Stroke questionnaire

    Directory of Open Access Journals (Sweden)

    Kang Byoung-Kab

    2012-04-01

    Full Text Available Abstract Background The present study was conducted to examine the reliability and validity of the ‘Korean Standard Pattern Identification for Stroke (K-SPI-Stroke’, which was developed and evaluated within the context of traditional Korean medicine (TKM. Methods Between September 2006 and December 2010, 2,905 patients from 11 Korean medical hospitals were asked to complete the K-SPI-Stroke questionnaire as a part of project ' Fundamental study for the standardization and objectification of pattern identification in traditional Korean medicine for stroke (SOPI-Stroke. Each patient was independently diagnosed by two TKM physicians from the same site according to one of four patterns, as suggested by the Korea Institute of Oriental Medicine: 1 a Qi deficiency pattern, 2 a Dampness-phlegm pattern, 3 a Yin deficiency pattern, or 4 a Fire-heat pattern. We estimated the internal consistency using Cronbach’s α coefficient, the discriminant validity using the means score of patterns, and the predictive validity using the classification accuracy of the K-SPI-Stroke questionnaire. Results The K-SPI-Stroke questionnaire had satisfactory internal consistency (α = 0.700 and validity, with significant differences in the mean of scores among the four patterns. The overall classification accuracy of this questionnaire was 65.2 %. Conclusion These results suggest that the K-SPI-Stroke questionnaire is a reliable and valid instrument for estimating the severity of the four patterns.

  7. Nuclear performance standards: Promoting efficient generation

    International Nuclear Information System (INIS)

    Nagelhout, M.

    1990-01-01

    Nuclear plant performance standards are designed to share the risks of operation associated with nuclear generation. Such standards often shift risks from ratepayers to utility shareholders, even without a finding of imprudence or mismanagement. The rationale underlying nuclear performance standards is that ratepayers should not be responsible for excessive replacement power costs incurred as a result of unreasonable decisions by utility management, especially because the high fixed costs of nuclear plants are already included in base rates. In addition, performance standards can be designed to provide incentives to reward utilities that achieve superior nuclear performance, for the benefit of both ratepayers and shareholders

  8. Standards development for the nuclear industry

    International Nuclear Information System (INIS)

    Domondon, D.B.

    The ushering of nuclear era in the Philippines with the construction of the PNPP-I (Philippine Nuclear Power Plant) necessitates the evolvement and use of nuclear standards as a tool for safety evaluation in the licensing process. The Department of Nuclear Regulation and Safeguards under the Philippine Atomic Energy Commission has as one of its responsibilities the establishment of regulatory standards to ensure safe operation of nuclear facilities. This article points out the needs for nuclear standards and the steps in standard development which involve an enormous amount of resources in terms of manpower, expertise and money. The staff of the Department of Nuclear Regulations and Safeguards (DNRS) does not intend to engage in the original development of standards; rather, it reviews standards in use elsewhere, specifically in the U.S. and adopts to local conditions. (author)

  9. Status of Korean nuclear industry and Romania-Korea cooperation in the field of nuclear power

    International Nuclear Information System (INIS)

    Lee, Myung Key

    2005-01-01

    The Kyoto Protocol on climate change has urged the world to explore ways of cutting down the greenhouse emissions, and it also boosted a number of nuclear power projects that is so-called the renaissance of nuclear power. Nuclear power has proven to be the cleanest energy source and one of the cheapest types of energies, compared with other energy sources. Korea began developing its nuclear power projects from the early 1970's. Since the first nuclear power plant Kori Unit 1, started commercial operation in 1978, Korea has continuously promoted the development of nuclear power projects, and today it operates 20 nuclear power units (17,716 MW), including 4 units of CANDU plants. Korea ranked No. 6 in the world in terms of installed capacity of nuclear power plants, and 40% of its domestic electricity generation comes from nuclear power plants. The average plant capacity factor was 95.5% in 2005, which is about 16% than the world average of around 79%. All the Korean nuclear power projects are led and implemented by Korea Hydro and Nuclear Power Co. (KHNP) which is the sole state-owned nuclear power project company spun off from Korea Electric Power Corporation (KEPCO) in 2001 as part of the government's program for electric industry restructuring. The cooperation between Romania and Korea in the nuclear power field began in March 2001. At industrial level a technical agreement between the Romanian Company Nuclearelectrica S.A. (SNN) and KHNP was signed in July 2003 for cooperation in Cernavoda NPP projects. The joint development of the Cernavoda NPP unit 3 was one of the major topics. Heavy water produced by Romanian Heavy Water plant at Drobeta Turnu Severin was supplied to KHNP (16 tones in 2001 and another 16 tones in 2004). The feasibility study for units 3 and 4 is being performed in two phases under leadership of SNN in cooperation with KHNP, AECL, ANSALDO and Deloitte and Touche as a financial advisor in Phase 2. It is expected that the appropriate securities

  10. Management plan for the Nuclear Standards Program

    International Nuclear Information System (INIS)

    1979-11-01

    This Management Plan was prepared to describe the manner in which Oak Ridge National Laboratory will provide technical management of the Nuclear Standards Program. The organizational structure that has been established within ORNL for this function is the Nuclear Standards Management Center, which includes the Nuclear Standards Office (NSO) already in existence at ORNL. This plan is intended to support the policies and practices for the development and application of technical standards in ETN projects, programs, and technology developments as set forth in a standards policy memorandum from the DOE Program Director for Nuclear Energy

  11. Status of Korean nuclear industry and Romania-Korea cooperation in nuclear field

    International Nuclear Information System (INIS)

    Myung-Key, Lee

    2005-01-01

    Current status of electric power in Korea is characterized by the end of August 2004 by a total installed capacity of about 62,000 MW while the total electricity generation is about 342,000 GWh. The installed capacity of nuclear power is 17,716 MW, sharing 29% of total installed capacity and presenting 38% of total electricity generation in Korea. In accordance with the provisions of the Long Term Energy Plan during the past 40 years, the installed capacity in Korea has been drastically increased. In the 1960's, major sources of electricity generation were locally-mined anthracite coal and hydro, but in the 1970's it was the imported oil. However, through diversification policy the dependence of the imported oil has been rapidly reduced and the share of coal , gas and nuclear generation has been steadily increased. According to the long-term power development plan updated last year, which is extended to 2017, the installed capacity in the year 2017 will be about 88,000 MW. At that time nuclear power will become the largest, sharing 30% and the shares of coal and gas fired power will be steadily decreased. Concerning the Nuclear Power Projects, there are four different nuclear power sites along the coast of Korean peninsula, Yonggwang, Kori, Wolsong and Ulchin. In addition to the currently operating 20 nuclear power plants, there are 6 more nuclear power plants under construction at Shin-Wolsong and Shin-Kori sites. Our efforts to enhance the technology, economy and safety of the nuclear power plants will be continuously pursued. Wolsong unclear power units 1, 2, 3 and 4 are CANDU type reactors which are same type as Romanian Cernavoda nuclear power plants. Operational performance, in terms of capacity factor of NPPs, has remained well above the world average and recorded 91.4% last year. Also, last year, the frequency of unplanned trip was 0.6 time per reactor. In 2004, ten NPPs achieved OCTF, which stands for One Cycle Trouble Free in 2004. Wolsong unit 1

  12. Future perspectives of human resources in nuclear technology - The Korean case

    International Nuclear Information System (INIS)

    Min, B.J.

    2007-01-01

    Full text: Synopsis. The prospects for growth for the nuclear power industry in the Republic of Korea, have improved notably in last few years, as the need for generating capacity grows to meet burgeoning energy demand and developmental needs, and as environment, climate change and energy supply security continue become matters of rising concern. Nuclear technology itself has also changed, with evolutionary and innovative changes in reactor design and safety measures. Nuclear technology development both requires and fosters human resource development (HRD). A continuous, consistent and well-managed programme of HRD is crucial to assure continuity over time in the needed capacities, skills and knowledge, and to establish and maintain a cadre of manpower variously trained in different nuclear-related skills and educated in nuclear relevant fields. It also fosters the development of spin-off industries and synergies. Productive and goal-oriented HRD and M is a dynamic long-term process that balances the dynamics of supply and demand of human resources with respect to the education, recruitment, maintenance and proper training of the human resources needed for industry operations as well as innovation. Such a programme in fact was the foundation for the birth of the Korean nuclear industry, with the government sponsoring nuclear-related- training and education for hundreds of persons under the tutelage of companies and countries overseas having experience with nuclear and related sciences and technology. This cadre, once repatriated, formed the nucleus for domestic training and education programmes as an integral part of nuclear energy development and consistent with national policies. HRD and M in Korea today comprises an educational network among academic and research institutes, government and industry. Forming such a cadre is not the result of a one-off training process, but must be planned and sustained consistently over time and its talents regularly applied

  13. Nuclear radiation moisture gauge calibration standard

    International Nuclear Information System (INIS)

    1977-01-01

    A hydrophobic standard for calibrating nuclear radiation moisture gauges is described. Each standard has physical characteristics and dimensions effective for representing to a nuclear gauge undergoing calibration, an infinite mass of homogeneous hydrogen content. Calibration standards are discussed which are suitable for use with surface gauges and with depth gauges. (C.F.)

  14. National standards for the nuclear industry

    International Nuclear Information System (INIS)

    Laing, W.R.; Corbin, L.T.

    1981-01-01

    Standards needs for the nuclear industry are being met by a number of voluntary organizations, such as ANS, ASTM, AWS, ASME, and IEEE. The American National Standards Institute (ANSI) coordinates these activities and approves completed standards as American National Standards. ASTM has two all-nuclear committees, E-10 and C-26. A C-26 subcommittee, Test Methods, has been active in writing analytical chemistry standards for twelve years. Thirteen have been approved as ANSI standards and others are ready for ballot. Work is continuing in all areas of the nuclear fuel cycle

  15. Nuclear standards: current issues and future trends

    International Nuclear Information System (INIS)

    Landis, J.W.

    1985-01-01

    A summary of the important issues that currently face the nuclear standards field is presented and a discussion of how each of these issues is being resolved is given. The economic benefits that properly developed standards produce are listed

  16. Site-Specific Atmospheric Dispersion Characteristics of Korean Nuclear Power Plant Sites

    International Nuclear Information System (INIS)

    Han, M. H.; Kim, E. H.; Suh, K. S.; Hwang, W. T.; Choi, Y. G.

    2001-01-01

    Site-specific atmospheric dispersion characteristics have been analyzed. The northwest and the southwest wind prevail on nuclear sites of Korea. The annual isobaric surface averaged for twenty years around Korean peninsula shows that west wind prevails. The prevailing west wind is profitable in the viewpoint of radiation protection because three of four nuclear sites are located in the east side. Large scale field tracer experiments over nuclear sites have been conducted for the purpose of analyzing the atmospheric dispersion characteristics and validating a real-time atmospheric dispersion and dose assessment system FADAS. To analyze the site-specific atmospheric dispersion characteristics is essential for making effective countermeasures against a nuclear emergency

  17. A seismic analysis of Korean standard PWR fuels under transition core conditions

    International Nuclear Information System (INIS)

    Kim, Hyeong Koo; Park, Nam Kyu; Jang, Young Ki; Kim, Jae Ik; Kim, Kyu Tae

    2005-01-01

    The PLUS7 fuel is developed to achieve higher thermal performance, burnup and more safety margin than the conventional fuel used in the Korean Standard Nuclear Plants (KSNPs) and to sustain structural integrity under increased seismic requirement in Korea. In this study, a series of seismic analysis have been performed in order to evaluate the structural integrity of fuel assemblies associated with seismic loads in the KSNPs under transition core conditions replacing the Guardian fuel, which is a resident fuel in the KSNP reactors, with the PLUS7 fuel. For the analysis, transition core seismic models have been developed, based on the possible fuel loading patterns. And the maximum impact forces on the spacer grid and various stresses acting on the fuel components have been evaluated and compared with the through-grid strength of spacer grids and the stress criteria specified in the ASME code for each fuel component, respectively. Then three noticeable parameters regarding as important parameters governing fuel assembly dynamic behavior are evaluated to clarify their effects on the fuel impact and stress response. As a result of the study, it has been confirmed that both the PLUS7 and the Guardian fuel sustain their structural integrity under the transition core condition. And when the damping ratio is constant, increasing the natural frequency of fuel assembly results in a decrease in impact force. The fuel assembly flexural stiffness has an effect increasing the stress of fuel assembly, but not the impact force. And the spacer grid stiffness is directly related with the impact force response. (author)

  18. The international dimensions of nuclear safety standards

    International Nuclear Information System (INIS)

    Reed, J.M.

    1992-01-01

    The paper reviews the activities of the major international organisations in the field of nuclear safety standards; the International Atomic Energy Agency (IAEA), the OECD's Nuclear Energy Agency (NEA) and the Commission of the European Communities. Each organisation encourages the concept of international nuclear safety standards. After Chernobyl, there were calls for some form of binding international nuclear safety standards. Many Member States of IAEA accepted these Codes as a suitable basis for formulating their national safety standards, but the prevailing view was that voluntary compliance with the Codes was the preferred path. With few reactor vendors in a limited international market, the time may be approaching when an internationally licensable nuclear reactor is needed. Commonly accepted safety standards would be a prerequisite. The paper discusses the issues involved and the complexities of standards making in the international arena. (author)

  19. A study on the food consumption rates for off-site radiological dose assessment around Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Gab Bock; Chung, Yang Geun

    2008-01-01

    The internal dose by food consumption mostly accounts for radiological dose of public around Nuclear Power Plants (NPPs). But, food consumption rates applied to off-site dose calculation in Korea which are the result of field investigation around Kori NPP by the KAERI (Korea Atomic Energy Research Institute) in 1988, are not able to reflect the latest dietary characteristics of Korean. The food consumption rates to be used for radiological dose assessment in Korea are based on the maximum individual of US NRC (Nuclear Regulatory Commission) Regulatory Guide 1.109. However, the representative individual of the critical group is considered in the recent ICRP (International Commission on Radiological Protection) recommendation and European nations' practice. Therefore, the study on the re-establishment of the food consumption rates for individual around nuclear power plant sites in Korea was carried out to reflect on the recent change of the Korean dietary characteristics and to apply the representative individual of critical group to domestic regulations. The ministry of Health and Welfare Affairs has investigated the food and nutrition of nations every 3 years based on the Law of National Health Improvement. The statistical data such as mean, standard deviation, various percentile values about food consumption rates to be used for the representative individual of the critical group were analyzed by using the raw data of the national food consumption survey in 2001∼2002. Also, the food consumption rates for maximum individual are re-estimated

  20. Quantification of brain images using Korean standard templates and structural and cytoarchitectonic probabilistic maps

    International Nuclear Information System (INIS)

    Lee, Jae Sung; Lee, Dong Soo; Kim, Yu Kyeong

    2004-01-01

    Population based structural and functional maps of the brain provide effective tools for the analysis and interpretation of complex and individually variable brain data. Brain MRI and PET standard templates and statistical probabilistic maps based on image data of Korean normal volunteers have been developed and probabilistic maps based on cytoarchitectonic data have been introduced. A quantification method using these data was developed for the objective assessment of regional intensity in the brain images. Age, gender and ethnic specific anatomical and functional brain templates based on MR and PET images of Korean normal volunteers were developed. Korean structural probabilistic maps for 89 brain regions and cytoarchitectonic probabilistic maps for 13 Brodmann areas were transformed onto the standard templates. Brain FDG PET and SPGR MR images of normal volunteers were spatially normalized onto the template of each modality and gender. Regional uptake of radiotracers in PET and gray matter concentration in MR images were then quantified by averaging (or summing) regional intensities weighted using the probabilistic maps of brain regions. Regionally specific effects of aging on glucose metabolism in cingulate cortex were also examined. Quantification program could generate quantification results for single spatially normalized images per 20 seconds. Glucose metabolism change in cingulate gyrus was regionally specific: ratios of glucose metabolism in the rostral anterior cingulate vs. posterior cingulate and the caudal anterior cingulate vs. posterior cingulate were significantly decreased as the age increased. 'Rostral anterior' / 'posterior' was decreased by 3.1% per decade of age (p -11 , r=0.81) and 'caudal anterior' / 'posterior' was decreased by 1.7% (p -8 , r=0.72). Ethnic specific standard templates and probabilistic maps and quantification program developed in this study will be useful for the analysis of brain image of Korean people since the difference

  1. Recent activities on nuclear codes and standards

    International Nuclear Information System (INIS)

    Minematsu, Akiyoshi; Ishimoto, Shozaburo; Honjin, Masao

    2000-01-01

    The technical codes and standards relating to the nuclear power stations in Japan are prepared by shapes of laws (ministerial ordinances and bulletins) issued by the government and obliged to comply with by 'the Law concerning the Regulations of Nuclear Material Substances, Nuclear Fuel Substances and Nuclear Reactors' and 'the Electricity Business Act' and of guides defined by the Nuclear Safety Commission, and further some private standards have been issued at a shape of complement of these laws and guides by receiving national recommendation. On the other hand, in the fields of electricity and heat facilities except atomic energy, simplification and feature stipulation of the national technical codes and standards was recently carried out, by which a system usable for the private standards in and out of Japan were prepared through approval of the private Japan Electrotechnical Standards and Codes Committee (JESC). As the nuclear field was now excepted from simultaneous transfer to the private standard and the standard application system, it is expected in future to realize similar transfer if possible and preparation of the private standards is now being advanced. Here were introduced on present state on technical codes and standards relating to the nuclear power generation facilities and recent trends on their private standardization. (G.K.)

  2. Nuclear spectrum influence on North Korean and Japanese identity constructs

    International Nuclear Information System (INIS)

    Fernandez-Gallois, Yohann

    2017-01-01

    This article introduces the concept of 'nuclear spectrum' which reflects the ability of nuclear weapons to produce effects in diplomatic and strategic fields. The author analyzes the influence of the American nuclear spectrum in East Asia and the interactions with the nuclear spectra of North Korea and Japan. He shows that the American nuclear umbrella deeply influences the inter-state relations between the two Korea and Japan

  3. Assessment of bone age in prepubertal healthy Korean children: Comparison among the Korean standard bone age chart, Greulich-Pyle method, and Tanner-Whitehouse method

    International Nuclear Information System (INIS)

    Kim Jeong Rye; Lee, Young Seok; Yu, Jee Suk

    2015-01-01

    To compare the reliability of the Greulich-Pyle (GP) method, Tanner-Whitehouse 3 (TW3) method and Korean standard bone age chart (KS) in the evaluation of bone age of prepubertal healthy Korean children. Left hand-wrist radiographs of 212 prepubertal healthy Korean children aged 7 to 12 years, obtained for the evaluation of the traumatic injury in emergency department, were analyzed by two observers. Bone age was estimated using the GP method, TW3 method and KS, and was calculated in months. The correlation between bone age measured by each method and chronological age of each child was analyzed using Pearson correlation coefficient, scatterplot. The three methods were compared using one-way analysis of variance. Significant correlations were found between chronological age and bone age estimated by all three methods in whole group and in each gender (R2 ranged from 0.87 to 0.9, p < 0.01). Although bone age estimated by KS was slightly closer to chronological age than those estimated by the GP and TW3 methods, the difference between three methods was not statistically significant (p > 0.01). The KS, GP, and TW3 methods show good reliability in the evaluation of bone age of prepubertal healthy Korean children without significant difference between them. Any are useful for evaluation of bone age in prepubertal healthy Korean children.

  4. Decision support for selecting exportable nuclear technology using the analytic hierarchy process: A Korean case

    International Nuclear Information System (INIS)

    Lee, Deok Joo; Hwang, Jooho

    2010-01-01

    The Korean government plans to increase strategically focused R and D investment in some promising nuclear technology areas to create export opportunities of technology in a global nuclear market. The purpose of this paper is to present a decision support process for selecting promising nuclear technology with the perspective of exportability by using the AHP based on extensive data gathered from nuclear experts in Korea. In this study, the decision criteria for evaluating the export competitiveness of nuclear technologies were determined, and a hierarchical structure for the decision-making process was systematically developed. Subsequently relative weights of decision criteria were derived using AHP methodology and the export competitiveness of nuclear technology alternatives was quantified to prioritize them. We discuss the implications of our results with a viewpoint toward national nuclear technology policy.

  5. Korean system of export control to support the commercial nuclear transfer to UAE

    International Nuclear Information System (INIS)

    Cho, Young Ho

    2011-01-01

    In December 2009, the Republic of Korea won the contract to build 4 1,400 MW nuclear power reactors worth USD 20 billion in the UAE. The states-owned KEPCO will complete the turnkey project to the UAE including design, engineering, construction, nuclear fuel, operations, maintenance and technical support. Since sensitive nuclear technologies convertible to military purpose can be spread by the transfer of commercial nuclear power plant, it is essential prerequisite to implement nuclear export control tenaciously and effectively. About twenty years have passed since the Republic of Korea introduced export control system in domestic laws and regulations. Marking a major historical milestone in 2009 by ranking among global nuclear suppliers, the Korean government made a major step forward in export control framework to support its next nuclear export goal. (orig.)

  6. Experience curve analysis on South Korean nuclear technology and comparative analysis with South Korean renewable technologies

    International Nuclear Information System (INIS)

    Kim, Dong Wook; Chang, Hyun Joon

    2012-01-01

    Increasing awareness on environmental damage and climate change has induced many nations to engage in green growth. South Korea, as one of the largest consumers of energy, is no exception and has shown its determination to pursue green growth in the future. In order to do so, South Korea plans to substitute fossil fuel with alternative sources in electricity generation. However, the key constraint to green growth is the high cost faced by renewable electricity generation. Fortunately, nuclear energy can serve as an economic alternative to fossil fuel. To achieve CO 2 emission reduction and faster economic growth, it is wise to analyze prospects of alternatives using experience curve framework. The results and industry background are consistent for nuclear technology, and the results suggest that nuclear should serve as the main substitute. Consideration of policy risk inherent in renewable also strengthens the argument. Renewable technologies, on the other hand, showed overstated learning capacity that is partially inconsistent with technological background. Nevertheless, the renewable (photovoltaic and fuel cell) should help nuclear marginally in substituting fossil fuel in South Korea's Electricity Generation. - Highlights: ► Progress ratios of renewable energy show great prospect. ► The policy risk is inherent in renewable and may overestimate its prospect. ► Nuclear sources are economic and less affected by policy risk. ► Fuel cell and photovoltaic should help nuclear marginally in green growth.

  7. A preliminary study on the cultural differences between Korean and Japanese organizations in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Hee; Lee, Yong Hee [KAERI, Daejeon (Korea, Republic of); Oh, Ingyu [Hanshin Univ., Seoul (Korea, Republic of); Do, Giang [Sol Bridge International School of Business, Daejeon (Korea, Republic of)

    2012-10-15

    The meltdowns of the Chernobyl and Fukushima I nuclear reactors are fundamentally linked to their organizational characteristics, as they caused severe social and economic disruptions with equally significant environmental and health related impacts. This shows that we have to find practical solutions to reactor safety from various organizational standpoints by introducing a systematic approach to the issue of organizational deficiencies and human errors. We posit that one of the fundamental causes of organizational deficiencies can be derived from an organizational culture. An organizational culture has both formal and informal types. Generally, organizational culture refers to the common beliefs, values, norms, symbols, and language systems that organizational members use when they add meaning to their organizational behavior within their specific organizations. The purpose of this study is threefold. First, we are interested in finding internal contradictions between Korean organizational culture and U.S.-derived organizational safety mechanisms applied to the operation of Korean NPPs (Nuclear Power Plants). We want to discern safety related problems that are thought to have occurred routinely within the parameters of Korean NPPs owing to the use of U.S. safety mechanisms. Second, we compare the Korean and Japanese organizational culture in NPP mainly on safety and comfort cultures in order to cope with the cultural problems. Third, we want to propose an alternative model of safety mechanisms that are more appropriate for Korean organizational culture, using a system dynamic model that we devised based on empirical observations from the NPPs and factors drawn from the extant literature as compared with Japanese organizational culture.

  8. A preliminary study on the cultural differences between Korean and Japanese organizations in nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Yong Hee; Lee, Yong Hee; Oh, Ingyu; Do, Giang

    2012-01-01

    The meltdowns of the Chernobyl and Fukushima I nuclear reactors are fundamentally linked to their organizational characteristics, as they caused severe social and economic disruptions with equally significant environmental and health related impacts. This shows that we have to find practical solutions to reactor safety from various organizational standpoints by introducing a systematic approach to the issue of organizational deficiencies and human errors. We posit that one of the fundamental causes of organizational deficiencies can be derived from an organizational culture. An organizational culture has both formal and informal types. Generally, organizational culture refers to the common beliefs, values, norms, symbols, and language systems that organizational members use when they add meaning to their organizational behavior within their specific organizations. The purpose of this study is threefold. First, we are interested in finding internal contradictions between Korean organizational culture and U.S.-derived organizational safety mechanisms applied to the operation of Korean NPPs (Nuclear Power Plants). We want to discern safety related problems that are thought to have occurred routinely within the parameters of Korean NPPs owing to the use of U.S. safety mechanisms. Second, we compare the Korean and Japanese organizational culture in NPP mainly on safety and comfort cultures in order to cope with the cultural problems. Third, we want to propose an alternative model of safety mechanisms that are more appropriate for Korean organizational culture, using a system dynamic model that we devised based on empirical observations from the NPPs and factors drawn from the extant literature as compared with Japanese organizational culture

  9. KoVariome: Korean National Standard Reference Variome database of whole genomes with comprehensive SNV, indel, CNV, and SV analyses.

    Science.gov (United States)

    Kim, Jungeun; Weber, Jessica A; Jho, Sungwoong; Jang, Jinho; Jun, JeHoon; Cho, Yun Sung; Kim, Hak-Min; Kim, Hyunho; Kim, Yumi; Chung, OkSung; Kim, Chang Geun; Lee, HyeJin; Kim, Byung Chul; Han, Kyudong; Koh, InSong; Chae, Kyun Shik; Lee, Semin; Edwards, Jeremy S; Bhak, Jong

    2018-04-04

    High-coverage whole-genome sequencing data of a single ethnicity can provide a useful catalogue of population-specific genetic variations, and provides a critical resource that can be used to more accurately identify pathogenic genetic variants. We report a comprehensive analysis of the Korean population, and present the Korean National Standard Reference Variome (KoVariome). As a part of the Korean Personal Genome Project (KPGP), we constructed the KoVariome database using 5.5 terabases of whole genome sequence data from 50 healthy Korean individuals in order to characterize the benign ethnicity-relevant genetic variation present in the Korean population. In total, KoVariome includes 12.7M single-nucleotide variants (SNVs), 1.7M short insertions and deletions (indels), 4K structural variations (SVs), and 3.6K copy number variations (CNVs). Among them, 2.4M (19%) SNVs and 0.4M (24%) indels were identified as novel. We also discovered selective enrichment of 3.8M SNVs and 0.5M indels in Korean individuals, which were used to filter out 1,271 coding-SNVs not originally removed from the 1,000 Genomes Project when prioritizing disease-causing variants. KoVariome health records were used to identify novel disease-causing variants in the Korean population, demonstrating the value of high-quality ethnic variation databases for the accurate interpretation of individual genomes and the precise characterization of genetic variations.

  10. The application of FIMS to the Korean nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Seung-Tae; Choi, Dae-Sik; Yang, Choong-Yeol

    2010-01-01

    The smart transmitters have been installed at selected systems of Ulchin Nuclear Units 5 and 6, and diagnosis and calibration for the smart transmitters have been carried out using the mobile calibration tools. In Shin-Kori Nuclear Units 1 and 2 and Shin-Wolsong Nuclear Units 1 and 2, which are under design and construction, the smart transmitters are installed in the places where total integrated radiation dose is below 10 Gy. FIMS (Field Instrument Management System) is applied to Shin-Kori Nuclear Units 1 and 2 and Shin-Wolsong Nuclear Units 1 and 2 to monitor and calibrate the smart transmitters remotely. FIMS is a centralized management system to allow the users to monitor the operating status, to perform the instrument diagnosis, and to carry out the calibration of locally mounted transmitters remotely during the commissioning and normal operation. (authors)

  11. Department of Energy Nuclear Energy Standards Program

    International Nuclear Information System (INIS)

    Silver, E.G.

    1980-01-01

    The policy with respect to the development and use of standards in the Department of Energy (DOE) programs concerned with maintaining and developing the nuclear option for the civilian sector (both in the form of the currently used light water reactors and for advanced concepts including the Liquid Metal Fast Breeder Reactor), is embodied in a Nuclear Standards Policy, issued in 1978, whose perspectives and philosophy are discussed

  12. A study on associations of Korean sample group for colors applied to the nuclear power plant control room

    Energy Technology Data Exchange (ETDEWEB)

    Oh, In Seok; Lee, Jung Woon; Lee, Yong Hee; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejeon (Korea); Lee, Dhong Ha [Suwon University, Whasung (Korea)

    2002-05-01

    Colors are widely used to warn risk levels and to attract attention of the public. Korea Standard Nuclear Reactor Control Room (KSNRCR) also uses several colors to differentiate warnings, priorities, status, borders, and messages based on the HF010 guideline. However the previous studies showed that the general public not engaged in a specific job domain had different associations of colors as regulated in the standards or the guidelines. It is also expected that the general public not engaged in nuclear power plant industry will have different color association system from the color coding system applied to the KSNRCR. So, this study was performed to show whether there is any difference between color association of a sample Korean group and the color meanings specified in the HF010 guideline. The general public not engaged in the nuclear power plant industry have no idea of the color usage in the nuclear control room. So we converted the specific color usage situation into similar but general situations. In questionnaire, we gave subjects the general situation where color coding is appled and alternative colors which were applied to the HF010 guidelines. And we asked the subjects to choose the colors proper to the situation and to rank the colors according to the degree of suitability. A hundred college students participated in the experiment. 10 refs., 7 tabs. (Author)

  13. Quantification of brain images using Korean standard templates and structural and cytoarchitectonic probabilistic maps

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jae Sung; Lee, Dong Soo; Kim, Yu Kyeong [College of Medicine, Seoul National Univ., Seoul (Korea, Republic of)] [and others

    2004-06-01

    Population based structural and functional maps of the brain provide effective tools for the analysis and interpretation of complex and individually variable brain data. Brain MRI and PET standard templates and statistical probabilistic maps based on image data of Korean normal volunteers have been developed and probabilistic maps based on cytoarchitectonic data have been introduced. A quantification method using these data was developed for the objective assessment of regional intensity in the brain images. Age, gender and ethnic specific anatomical and functional brain templates based on MR and PET images of Korean normal volunteers were developed. Korean structural probabilistic maps for 89 brain regions and cytoarchitectonic probabilistic maps for 13 Brodmann areas were transformed onto the standard templates. Brain FDG PET and SPGR MR images of normal volunteers were spatially normalized onto the template of each modality and gender. Regional uptake of radiotracers in PET and gray matter concentration in MR images were then quantified by averaging (or summing) regional intensities weighted using the probabilistic maps of brain regions. Regionally specific effects of aging on glucose metabolism in cingulate cortex were also examined. Quantification program could generate quantification results for single spatially normalized images per 20 seconds. Glucose metabolism change in cingulate gyrus was regionally specific: ratios of glucose metabolism in the rostral anterior cingulate vs. posterior cingulate and the caudal anterior cingulate vs. posterior cingulate were significantly decreased as the age increased. 'Rostral anterior' / 'posterior' was decreased by 3.1% per decade of age (p<10{sup -11}, r=0.81) and 'caudal anterior' / 'posterior' was decreased by 1.7% (p<10{sup -8}, r=0.72). Ethnic specific standard templates and probabilistic maps and quantification program developed in this study will be useful for the analysis

  14. ENVI Model Development for Korean Nuclear Spent Fuel Options Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Sunyoung; Jeong, Yon Hong; Han, Jae-Jun; Lee, Aeri; Hwang, Yong-Soo [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2015-10-15

    The disposal facility of the spent nuclear fuel will be operated from 2051. This paper presents the ENVI code developed by GoldSim Software to simulate options for managing spent nuclear fuel (SNF) in South Korea. The ENVI is a simulator to allow decision-makers to assist to evaluate the performance for spent nuclear fuel management. The multiple options for managing the spent nuclear fuel including the storage and transportation are investigated into interim storage, permanent disposal in geological repositories and overseas and domestic reprocessing. The ENVI code uses the GoldSim software to simulate the logistics of the associated activities. The result by the ENVI model not only produces the total cost to compare among the multiple options but also predict the sizes and timings of different facilities required. In order to decide the policy for spent nuclear management this purpose of this paper is to draw the optimum management plan to solve the nuclear spent fuel issue in the economical aspects. This paper is focused on the development of the ENVI's logic and calculations to simulate four options(No Reprocessing, Overseas Reprocessing, Domestic Reprocessing, and Overseas and Domestic Reprocessing) for managing the spent nuclear fuel in South Korea. The time history of the spent nuclear fuel produced from both the existing and future NPP's can be predicted, based on the Goldsim software made available very user friendly model. The simulation result will be used to suggest the strategic plans for the spent nuclear fuel management.

  15. ENVI Model Development for Korean Nuclear Spent Fuel Options Analysis

    International Nuclear Information System (INIS)

    Chang, Sunyoung; Jeong, Yon Hong; Han, Jae-Jun; Lee, Aeri; Hwang, Yong-Soo

    2015-01-01

    The disposal facility of the spent nuclear fuel will be operated from 2051. This paper presents the ENVI code developed by GoldSim Software to simulate options for managing spent nuclear fuel (SNF) in South Korea. The ENVI is a simulator to allow decision-makers to assist to evaluate the performance for spent nuclear fuel management. The multiple options for managing the spent nuclear fuel including the storage and transportation are investigated into interim storage, permanent disposal in geological repositories and overseas and domestic reprocessing. The ENVI code uses the GoldSim software to simulate the logistics of the associated activities. The result by the ENVI model not only produces the total cost to compare among the multiple options but also predict the sizes and timings of different facilities required. In order to decide the policy for spent nuclear management this purpose of this paper is to draw the optimum management plan to solve the nuclear spent fuel issue in the economical aspects. This paper is focused on the development of the ENVI's logic and calculations to simulate four options(No Reprocessing, Overseas Reprocessing, Domestic Reprocessing, and Overseas and Domestic Reprocessing) for managing the spent nuclear fuel in South Korea. The time history of the spent nuclear fuel produced from both the existing and future NPP's can be predicted, based on the Goldsim software made available very user friendly model. The simulation result will be used to suggest the strategic plans for the spent nuclear fuel management

  16. How the South Korean energy program has been saving the US nuclear industry

    International Nuclear Information System (INIS)

    Shorrock, T.

    1982-01-01

    The view is given that the US government financed South Korea's nuclear program at taxpayer expense. Westinghouse Electric Co., which supplied the equipment for Korea's reactors, was said to be the taxpayers' beneficiary. US participation was justified on grounds of commercial benefits to US companies, fuel suppliers, and world prestige as a promoter of peaceful nuclear applications and assistance to developing countries. The Export-Import Bank provided funding after strong urging by the US Embassy in Korea and Westinghouse. The author states that pressure was also put on the Korean government to award contracts to US suppliers. The negotiations have spanned periods of unrest in Korea

  17. ISO: international standards development for nuclear technology

    International Nuclear Information System (INIS)

    Becker, K.

    1981-01-01

    The importance of internationally recognized standards for nuclear technology and safety is rapidly increasing for technical as well as economical and political reasons such as public acceptance and nuclear technology transfer to developing countries. The need for such standards is also evident because of the large number of nuclear installations sited close to international borders, and the export of nuclear installations from relatively few supplier countries to a large number of user countries. It is the purpose of this report to describe briefly the history, organizational structures and procedures, goals, accomplishments, problems, and future needs of the relevant activities of the International Organization for Standardization (ISO). ISO is composed of the partly governmental, partly non-governmental national standards bodies of 86 countries including China. The work of its Technical Committee (TC) 85 'Nuclear Energy' is mostly concerned with industrial applications, contractual aspects and international communication, for the benefit of both developed and developing countries. It works in close liaison with IAEA, which develops Codes and Guides addressed mainly to the regulatory aspects of nuclear power plants in developing countries. ISO/TC 85 has four sub-committees dealing with: (a) Terminology, Definitions, Units and Symbols (Secretariat USA, four working groups (WGs)); (b) Radiation Protection (Secretariat France, ten WGs); (c) Power Reactor Technology (Secretariat Sweden, nine WGs); (d) Nuclear Fuel Technology (Secretariat F.R. Germany, seven WGs). (author)

  18. Nonreactor nuclear facilities: standards and criteria guide

    International Nuclear Information System (INIS)

    Brynda, W.J.; Junker, L.; Karol, R.C.; Lobner, P.R.; Goldman, L.A.

    1981-09-01

    This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE Order 5480.1, Chapter V, Safety of Nuclear Facilities. The guidance and criteria provided are directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. These general guidelines may have limited applicability to subsurface facilities such as waste repositories. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines

  19. Nonreactor nuclear facilities: Standards and criteria guide

    International Nuclear Information System (INIS)

    Brynda, W.J.; Scarlett, C.H.; Tanguay, G.E.; Lobner, P.R.

    1986-09-01

    This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE 5480.1A, Chapter V, ''Safety of Nuclear Facilities.'' The guidance and criteria provided is directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, conduct of operations, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines. 25 figs., 62 tabs

  20. Nuclear radiation moisture gauge calibration standard

    International Nuclear Information System (INIS)

    Berry, R.L.

    1981-01-01

    A hydrophobic standard for calibrating radiation moisture gauges is described. This standard has little or no affinity for water and accordingly will not take up or give off water under ambient conditions of fluctuating humidity in such a manner as to change the hydrogen content presented to a nuclear gauge undergoing calibration. (O.T.)

  1. Korean students' behavioral change toward nuclear power generation through education

    International Nuclear Information System (INIS)

    Han, Eun Ok; Kim, Jae Rok; Choi, Yoon Seok

    2014-01-01

    As a result of conducting a 45 minute-long seminar on the principles, state of use, advantages, and disadvantages of nuclear power generation for Korean elementary, middle, and high school students, the levels of perception including the necessity (p<0.017), safety (p<0.000), information acquisition (p<0.000), and subjective knowledge (p<0.000), objective knowledge (p<0.000), attitude (p<0.000), and behavior (p<0.000) were all significantly higher. This indicates that education can be effective in promoting widespread social acceptance of nuclear power and its continued use. In order to induce behavior change toward positive judgments on nuclear power generation, it is necessary to focus on attitude improvement while providing the information in all areas related to the perception, knowledge, attitude, and behavior. Here, the positive message on the convenience and the safety of nuclear power generation should be highlighted.

  2. Korean students' behavioral change toward nuclear power generation through education

    Energy Technology Data Exchange (ETDEWEB)

    Han, Eun Ok; Kim, Jae Rok; Choi, Yoon Seok [Dept. of Education and Research, Korea Academy of Nuclear Safety, Seoul (Korea, Republic of)

    2014-10-15

    As a result of conducting a 45 minute-long seminar on the principles, state of use, advantages, and disadvantages of nuclear power generation for Korean elementary, middle, and high school students, the levels of perception including the necessity (p<0.017), safety (p<0.000), information acquisition (p<0.000), and subjective knowledge (p<0.000), objective knowledge (p<0.000), attitude (p<0.000), and behavior (p<0.000) were all significantly higher. This indicates that education can be effective in promoting widespread social acceptance of nuclear power and its continued use. In order to induce behavior change toward positive judgments on nuclear power generation, it is necessary to focus on attitude improvement while providing the information in all areas related to the perception, knowledge, attitude, and behavior. Here, the positive message on the convenience and the safety of nuclear power generation should be highlighted.

  3. Implications of a North Korean Nuclear Weapons Program

    Energy Technology Data Exchange (ETDEWEB)

    Lehman, R.F. II

    1993-07-01

    The Democratic People`s Republic of Korea (DPRK) is one of the Cold War`s last remaining totalitarian regimes. Rarely has any society been as closed to outside influences and so distant from political, economic, and military developments around the globe. In 1991 and in 1992, however, this dictatorship took a number of political steps which increased Pyongyang`s interaction with the outside world. Although North Korea`s style of engagement with the broader international community involved frequent pauses and numerous steps backward, many observers believed that North Korea was finally moving to end its isolated, outlaw status. As the end of 1992 approached, however, delay and obstruction by Pyongyang became intense as accumulating evidence suggested that the DPRK, in violation of the nuclear Non-Proliferation Treaty (NPT), was seeking to develop nuclear weapons. On March 12, 1993, North Korea announced that it would not accept additional inspections proposed by the International Atomic Energy Agency (IAEA) to resolve concerns about possible violations and instead would withdraw from the Treaty. Pyongyang`s action raised the specter that, instead of a last act of the Cold War, North Korea`s diplomatic maneuvering would unravel the international norms that were to be the basis of stability and peace in the post-Cold War era. Indeed, the discovery that North Korea was approaching the capability to produce nuclear weapons suggested that the nuclear threat, which had been successfully managed throughout the Cold War era, could increase in the post-Cold War era.

  4. IAEA team to visit North Korean nuclear facilities

    International Nuclear Information System (INIS)

    2002-01-01

    A technical team from the IAEA will visit nuclear facilities in the Nyongbyon area of the Democratic People's Republic of Korea (DPRK) from 15-19 January. The visit will include the Isotope Production Laboratory, an installation that the DPRK has stated was involved in the early stages of development of their nuclear programme. Since 1993, the IAEA has been unable to fully implement its comprehensive safeguards agreement with the DPRK, and has been therefore unable to verify the completeness and correctness of the DPRK's initial 1992 declaration of its nuclear inventory. In May 2001, the IAEA proposed to the DPRK concrete steps that need to be carried out in that verification process, and indicated its readiness to start implementing these measures immediately. At a technical meeting between the DPRK and the IAEA in November 2001, the DPRK did not agree to promptly start to implement those proposals, citing the delay in implementation of the USA/DPRK Agreed Framework as the principal reason for declining. However, the DPRK did agree to a visit, not an inspection, by IAEA inspectors to the Isotope Production Laboratory. The DPRK withdrew its membership from the Agency in June 1994. The Director General encourages the DPRK to normalize its relations with the IAEA including resumption of full safeguards inspections

  5. Selecting safety standards for nuclear power plants

    International Nuclear Information System (INIS)

    1981-01-01

    Today, many thousands of documents are available describing the requirements, guidelines, and industrial standards which can be used as bases for a nuclear power plant programme. Many of these documents relate to nuclear safety which is currently the focus of world-wide attention. The multitude of documents available on the subject, and their varying status and emphasis, make the processes of selection and implementation very important. Because nuclear power plants are technically intricate and advanced, particularly in relation to the technological status of many developing countries, these processes are also complicated. These matters were the subject of a seminar held at the Agency's headquarters in Vienna last December. The IAEA Nuclear Safety Standards (NUSS) programme was outlined and explained at the Seminar. The five areas of the NUSS programme for nuclear power plants cover, governmental organization, siting, design; operation; quality assurance. In each area the Agency has issued Codes of Practice and is developing Safety Guides. These provide regulatory agencies with a framework for safety. The Seminar recognized that the NUSS programme should enable developing countries to identify priorities in their work, particularly the implementation of safety standards. The ISO activities in the nuclear field are carried out in the framework of its Technical Committee 85 (ISO/TC85). The work is distributed in sub-committees. Seminar on selection and implementation of safety standards for nuclear power plants, jointly organized by the IAEA and the International Organization for Standardization (ISO), and held in Vienna from 15 to 18 December 1980 concerned with: terminology, definitions, units and symbols (SC-1), radiation protection (SC-2), power reactor technology (SC-3), nuclear fuel technology (SC-5). There was general agreement that the ISO standards are complementary to the NUSS codes and guides. ISO has had close relations with the IAEA for several years

  6. Just war and nuclear weapons : just war theory and its application to the Korean nuclear weapons issue in Korean Christianity

    OpenAIRE

    Son, Changwan

    2009-01-01

    This thesis is primarily an application of the Christian tradition of Just War to the problems arising from the basing of US nuclear weapons in South Korea and the development of nuclear weapons by the regime in the North. The Christian theology of Just War has developed over the last two thousand years, adapting as first Christianity became the state religion of the Roman Empire, through the break down of any enforceable norms in Europe‘s 'Dark Ages‘, to the emergence of the concept of th...

  7. Harmonized technical standards in the nuclear field

    International Nuclear Information System (INIS)

    Carbone, Ferdinando

    1976-01-01

    The need was felt of harmonizing and gradually standardizing technical norms, from the well-known Anglo-Saxon type codes of practice to the equally well-known recommendations of the International Commission on Radiological Protection (ICRP). The latter provide the basis for the Euratom Directives (basic standards), which, following their adoption, were embodied in the national laws of community Member countries. ISO (International Standardization Organization) is active in the nuclear technical regulations field, in particular through its Committee ISO/TC 85 ''Nuclear Energy'' at international level and, in Italy, through the National Italian Unification Agency (UNI) and its Nuclear Unification Commission (UNICEN). At its XI plenary meeting this body, on the proposal of the Secretary-General, set up a Study Group to promote revision of the regulation in force and coordination between legislation and development of UNICEN standards, considered as a set of integrative industrial technical standards. CISDEN, the Italian Nuclear Energy Forum (FIEN) and other interested organizations have been invited to collaborate in this work. (N.E.A.)

  8. Analysis of Korean Nuclear Fuel Cycle System by Using DANESS Code

    International Nuclear Information System (INIS)

    Jeong, Chang Joon

    2009-08-01

    Korean fast reactor scenarios have been analyzed for various kinds of conversion ratio (CR) by the DANESS system dynamic analysis code. The once-through fuel cycle analysis was modeled based on the Korean 'National Energy Basic Plan' up to 2030 and a postulated nuclear demand growth rate until 2150. The fast reactor scenario analysis has been performed for three kinds of conversion ratios such as 0.3, 0.61 and 1.0. Through the calculations, the nuclear reactor deployment scenario, front-end cycle, back-end cycle, and long-term heat load have been investigated. From the once-through results, it is shown that the nuclear power demand would be ∼70 GWe and the total amount of the spent fuel accumulated by 2150 would be ∼168000 t. The fast reactor (FR) scenario analysis results show that the spent fuel inventory and out-pile transuranic element (TRU) can be reduced by increasing the fast reactor conversion ratio. Furthermore, the long-term heat load of spent fuel decreases with increasing the conversion ratio. However, it is known that the deployment of a fast reactor of low conversion ratio does not much reduce the spent fuel and out-pile TRU inventory due to the fast reactor deployment limitation which is related to the availability of TRU

  9. Rape Myth Acceptance among Korean College Students: The Roles of Gender, Attitudes toward Women, and Sexual Double Standard

    Science.gov (United States)

    Lee, Joohee; Kim, Jinseok; Lim, Hyunsung

    2010-01-01

    The purpose of the current study was to examine factors that influence rape myths among Korean college students. This study was particularly interested in the ways in which attitudes toward women and sexual double standard affect the relationship between gender and rape myths. Although the incidence of rape is a common concern in many current…

  10. The nuclear safety standards of IAEA (NUSS)

    International Nuclear Information System (INIS)

    Andres, H.

    1980-01-01

    The lecture will give an overview of the Agency's Safety Standards for Nuclear Power Plants: its range and its current state of development. The general contents of the documents will be presented, and the procedures used for their development will be briefly described. (orig.)

  11. Standards: An international framework for nuclear safety

    International Nuclear Information System (INIS)

    Versteeg, J.

    2000-01-01

    The IAEA, uniquely among international organizations concerned with the use of radiation, radioactive materials and nuclear energy, has statutory functions to establish safety standards and to provide for their application in Member States. The IAEA also contributes towards another major element of the 'global safety culture', namely the establishment of legally binding international agreements on safety related issues. (author)

  12. Standardization's role in revitalizing the nuclear option

    International Nuclear Information System (INIS)

    Ward, J.E.

    1986-01-01

    Considering the moribund status of the nuclear industry, something has to be done in the near-term to reverse the decaying economics of nuclear power. Standardization can turn around nuclear economics in the short term and in the longer term can foster a significant return to nuclear power. In the short term the industry needs to take advantage of those current designs that have proved their worth by excellent operating records. These designs can be replicated taking advantage of the complete status of the design and the construction techniques already in place. In the longer term it needs to develop preapproved designs and sites. Further, it must develop a discipline within the system of regulation as well as within the utility management to accept a power design as is. They cannot afford customized regulation nor customized design. Traditional institutional structures may also be up for grabs as utilities struggle to be more cost-effective. Generating companies may plan a significant role in the future of electric utilities. This kind of emphasis will also provide an impetus for the use of cost-effective, standardized designs that can be the catalyst for nuclear power's resurgence

  13. Standards for Endovascular Neurosurgical Training and Certification of the Society of Korean Endovascular Neurosurgeons 2013

    Science.gov (United States)

    Shin, Dong-Seong; Park, Sukh-Que; Kang, Hyun-Seung; Yoon, Seok-Mann; Cho, Jae-Hoon; Lim, Dong-Jun; Baik, Min-Woo; Kwon, O Ki

    2014-01-01

    The need for standard endovascular neurosurgical (ENS) training programs and certification in Korea cannot be overlooked due to the increasing number of ENS specialists and the expanding ENS field. The Society of Korean Endovascular Neurosurgeons (SKEN) Certification Committee has prepared training programs and certification since 2010, and the first certificates were issued in 2013. A task force team (TFT) was organized in August 2010 to develop training programs and certification. TFT members researched programs and systems in other countries to develop a program that best suited Korea. After 2 years, a rough draft of the ENS training and certification regulations were prepared, and the standard training program title was decided. The SKEN Certification Committee made an official announcement about the certification program in March 2013. The final certification regulations comprised three major parts: certified endovascular neurosurgeons (EN), certified ENS institutions, and certified ENS training institutions. Applications have been evaluated and the results were announced in June 2013 as follows: 126 members received EN certification and 55 hospitals became ENS-certified institutions. The SKEN has established standard ENS training programs together with a certification system, and it is expected that they will advance the field of ENS to enhance public health and safety in Korea. PMID:24851145

  14. Status of operation of radionuclides assay system in Korean nuclear power plant

    International Nuclear Information System (INIS)

    Hwang, K.H.; Lee, K.J.; Jeong, C.W.; Ahn, S.M.

    2003-01-01

    In Korea, 17 nuclear power plants composed of 13 pressurized water reactors and 4 CANDU reactors are currently in operation. The cumulative amounts of low and intermediate level radioactive waste in nuclear power plant reached 58,718 drums (unit: 200 liter) in 2001. Efforts to construct LILW disposal facility are continued and its first operation is planned in the year 2008. Its first stage capacity is assumed to be 100,000 drums and total capacity will reach to 800,000 drums. Radwaste disposal site selection is an urgent national project at present time. Regulations and guidelines require detailed information about the radioactive waste package and its contents prior to the transport to the disposal sites. The Enforcement Decree of the Korean Atomic Energy Act (articles 234-17) requires the Minister of Science and Technology (MOST) of Korea to establish regulation for the waste acceptance (MOST notice. 1196-10). It requires detailed information about the radioactive waste package and its contents such as activity of radionuclides, total activities, types and characteristics of waste. For the measurement of the concentrations and activities of radionuclides in radwaste drum, a radionuclides assay system is installed at Korean nuclear power plant (KORI site) in 1996. The waste drum can be measured in the vertical direction with eight vertical segments while in the radial direction also with eight segments. Using this measurement method, homogeneous and non-homogeneous waste drum can be measured. Scaling factor methods have been played a dominant role in the determination of the radionuclides concentration in this system. For corrosion product, generic scaling factors were used due to the similarity and better-characterized properties of Korean analyzed data as compared with the worldwide data base of PWR industry. For fission product and TRU nuclides, it is not easy to determine the generic scaling factors. Thus simple model reflecting the operation history of power

  15. A study on the direction for the development of the Korean nuclear R and D system toward the globalization

    International Nuclear Information System (INIS)

    Won, Byung Chul; Chung, Yun Ho; Kim, Myung Ro

    1994-12-01

    This study explores future directions for the development of the Korean nuclear R and D system by comparing the nuclear R and D systems in the US, France, Japan, and Canada. In an effort to search for appropriate directions, this study analyzed characteristics of the nuclear R and D systems in advanced nations in the following areas; (1) configuration of nuclear R and D, (2) morphological characteristics of major nuclear R and D organization, (3) evaluation of R and D performance, general management issues such as leadership, coordination, culture, etc., and (4) inter- organizationals with government agencies, utilities, and other regulatory organizations. On the basis of comparing the nuclear R and D system in Korea with those in the US, France, Japan, and Canada, this study tries to develop recommendations for the future directions of the Korean nuclear R and D system. The results of this research can serve as a reference to a long-term development plan for the Korean nuclear R and D system. 23 tabs., 4 figs., 34 refs. (Author)

  16. A study on the direction for the development of the Korean nuclear R and D system toward the globalization

    International Nuclear Information System (INIS)

    Won, Byung Chul; Jeong, Yeun Ho; Kim, Myung Ro; Kim, Young Pyung

    1996-02-01

    The purpose of this study is to explore future directions for the development of the Korean nuclear research system by comparing the nuclear R and D systems in the U.S., France, Japan, and Canada. In an effort to search for appropriate directions, this study analyzed the characteristics of the nuclear research systems in advanced nations in the following areas; 1. configuration of nuclear R and D, 2. morphological characteristics of major nuclear R and D organization, 3. evaluation of R and D performance, general management issues such as leadership, coordination, culture, etc., and 4. inter-organizationals with government agencies, utilities, and other regulatory organizations. On the basis of comparing the nuclear R and D system in Korea with those in the U.S., France, Japan, and Canada, this study tries to develop recommendations for the future directions of the Korean nuclear R and D system. The results of this research can serve as a reference to a long-term development plan for the Korean nuclear R and D system. 21 tabs., 11 figs., 36 refs. (Author)

  17. A study on the direction for the development of the Korean nuclear R and D system toward the globalization

    Energy Technology Data Exchange (ETDEWEB)

    Won, Byung Chul; Jeong, Yeun Ho; Kim, Myung Ro [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); Kim, Young Pyung [Korea Univ., Seoul (Korea, Republic of)

    1996-02-01

    The purpose of this study is to explore future directions for the development of the Korean nuclear research system by comparing the nuclear R and D systems in the U.S., France, Japan, and Canada. In an effort to search for appropriate directions, this study analyzed the characteristics of the nuclear research systems in advanced nations in the following areas; 1. configuration of nuclear R and D, 2. morphological characteristics of major nuclear R and D organization, 3. evaluation of R and D performance, general management issues such as leadership, coordination, culture, etc., and 4. inter-organizationals with government agencies, utilities, and other regulatory organizations. On the basis of comparing the nuclear R and D system in Korea with those in the U.S., France, Japan, and Canada, this study tries to develop recommendations for the future directions of the Korean nuclear R and D system. The results of this research can serve as a reference to a long-term development plan for the Korean nuclear R and D system. 21 tabs., 11 figs., 36 refs. (Author).

  18. A study on the direction for the development of the Korean nuclear R and D system toward the globalization

    Energy Technology Data Exchange (ETDEWEB)

    Won, Byung Chul; Chung, Yun Ho; Kim, Myung Ro [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-12-01

    This study explores future directions for the development of the Korean nuclear R and D system by comparing the nuclear R and D systems in the US, France, Japan, and Canada. In an effort to search for appropriate directions, this study analyzed characteristics of the nuclear R and D systems in advanced nations in the following areas; (1) configuration of nuclear R and D, (2) morphological characteristics of major nuclear R and D organization, (3) evaluation of R and D performance, general management issues such as leadership, coordination, culture, etc., and (4) inter- organizationals with government agencies, utilities, and other regulatory organizations. On the basis of comparing the nuclear R and D system in Korea with those in the US, France, Japan, and Canada, this study tries to develop recommendations for the future directions of the Korean nuclear R and D system. The results of this research can serve as a reference to a long-term development plan for the Korean nuclear R and D system. 23 tabs., 4 figs., 34 refs. (Author).

  19. Materials Integrity Analysis for Application of Hyper Duplex Stainless Steels to Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Chang, Hyun Young; Park, Heung Bae; Park, Yong Soo; Kim, Soon Tae; Kim, Young Sik; Kim, Kwang Tae; Jhang, Yoon Young

    2010-01-01

    Hyper duplex stainless steels have been developed in Korea for the purpose of application to the seawater system of Korean nuclear power plants. This system supplies seawater to cooling water heat exchanger tubes, related pipes and chlorine injection system. In normal operation, seawater is supplied to heat exchanger through the exit of circulating water pump headers, and the heat exchanged sea water is extracted to the discharge pipes in circulating water system connected to the circulating water discharge lines. The high flow velocity of some part of seawater system in nuclear power plants accelerates damages of components. Therefore, high strength and high corrosion resistant steels need to be applied for this environment. Hyper duplex stainless steel (27Cr-7.0Ni-2.5Mo-3.2W-0.35N) has been newly developed in Korea and is being improved for applying to nuclear power plants. In this study, the physical and mechanical properties and corrosion resistance of newly developed materials are quantitatively evaluated in comparative to commercial stainless steels in other countries. The properties of weld and HAZ (heat affected zone) are analyzed and the best compositions are suggested. The optimum conditions in welding process are derived for ensuring the volume fraction of ferrite(α) and austenite(γ) in HAZ and controlling weld cracks. For applying these materials to the seawater heat exchanger, CCT and CPT in weldments are measured. As a result of all experiments, it was found that the newly developed hyper duplex stainless steel WREMBA has higher corrosion resistance and mechanical properties than those of super austenitic stainless steels including welded area. It is expected to be a promising material for seawater systems of Korean nuclear power plants

  20. Third North Korean nuclear test: what is the state of the North's programme?

    International Nuclear Information System (INIS)

    Sitt, Bernard

    2013-02-01

    Two months ago, following North Korea's Unha-3 launch, which put a small satellite into orbit, this publication discussed the possibility of a third North Korean nuclear test. As expected, Pyongyang remained true to its traditional policy of provocation. With carefully calculated timing, it carried out a third nuclear test on 12 February, just hours after Barack Obama's State of the Union address, four days before former leader Kim Jong-il's birthday, and on the eve of the investiture of the new South Korean president on the 25 February. Moreover, the North Korean regime is billing this test as a riposte to the new round of sanctions adopted on by the Security Council on 22 January following the Unha-3 launch in December, as it announced on the 24 January. Yet, aside from the associated posturing, this test confirms, if more confirmation were needed, the North's determination to develop an effective nuclear deterrent. The use of the term miniaturisation is certainly in part a propaganda exercise (can actual miniaturisation be achieved after three nuclear tests, one or two of whose success is highly doubtful?). Nonetheless, North Korea has clearly made progress in developing a nuclear weapon and an intercontinental ballistic missile derived from the Taepodong-2, and has promised to carry out further ballistic launches. Without a doubt, even if the North is a long way from possessing what we would consider an operational nuclear capability, its determination has helped it to make progress, and the country shows no signs of wanting to change course. In light of this fact, what can the international community do beyond existing and future sanctions regimes? Doubtless very little. China, which continues to support the North and which has been known in the past to exert influence on Pyongyang, has expressed its firm displeasure as to the North's activities but appears to have no leverage over Kim Jong-un. The Six-Party talks have little chance of being revived, as North

  1. Classification of Korean native pear based on a standard set of microsatellite loci

    Science.gov (United States)

    After analysis with 12 microsatellite loci previously selected for use by ECPGR, 34 Korean pear accessions were classified into 3 groups. Group I included 4 Korean pea pears and one accession of P. calleryana. Group II contained 12 cultivars including 7 accessions presumed to belong to P. pyrifolia....

  2. Global Zero and Deterrence Credibility : A Critical Analysis of Obama`s Nuclear Policy and Extended Nuclear Deterrence Credibility on the Korean Peninsula

    OpenAIRE

    Ganss, Mathias

    2012-01-01

    This thesis is a qualitative case study analysis of the whether the nuclear policies of President Obama has weakened the U.S. extended nuclear deterrence credibility on the Korean Peninsula. To answer this, the thesis employs two strategies: First, two variables are discussed; a nuclear capabilities-variable; and a nuclear policy-variable. The purpose is to assess the impact the New START treaty has on U.S. nuclear capabilities, and to assess the implications of Obama`s nuclear policy, expres...

  3. Cross-Cultural Aspect of Behavior Assessment System for Children-2, Parent Rating Scale-Child: Standardization in Korean Children

    Science.gov (United States)

    Song, Jungeun; Leventhal, Bennett L.; Koh, Yun-Joo; Cheon, Keun-Ah; Hong, Hyun Ju; Kim, Young-Key; Cho, Kyungjin; Lim, Eun-Chung; Park, Jee In

    2017-01-01

    Purpose Our study aimed to examine psychometric properties and cross-cultural utility of the Behavior Assessment System for Children-2, Parent Rating Scale-Child (BASC-2 PRS-C) in Korean children. Materials and Methods Two study populations were recruited: a general population sample (n=2115) of 1st to 6th graders from 16 elementary schools and a clinical population (n=219) of 6–12 years old from 5 child psychiatric clinics and an epidemiological sample of autism spectrum disorder. We assessed the validity and reliability of the Korean version of BASC-2 PRS-C (K-BASC-2 PRS-C) and compared subscales with those used for US populations. Results Our results indicate that the K-BASC-2 PRS-C is a valuable instrument with reliability and validity for measuring developmental psychopathology that is comparable to those in Western population. However, there were some differences noted in the mean scores of BASC-2 PRS-C between Korean and US populations. Conclusion K-BASC-2 PRS-C is an effective and useful instrument with psychometric properties that permits measurement of general developmental psychopathology. Observed Korean-US differences in patterns of parental reports of children's behaviors indicate the importance of the validation, standardization and cultural adaptation for tools assessing psychopathology especially when used in populations different from those for which the instrument was originally created. PMID:28120577

  4. Cross-Cultural Aspect of Behavior Assessment System for Children-2, Parent Rating Scale-Child: Standardization in Korean Children.

    Science.gov (United States)

    Song, Jungeun; Leventhal, Bennett L; Koh, Yun Joo; Cheon, Keun Ah; Hong, Hyun Ju; Kim, Young Key; Cho, Kyungjin; Lim, Eun Chung; Park, Jee In; Kim, Young Shin

    2017-03-01

    Our study aimed to examine psychometric properties and cross-cultural utility of the Behavior Assessment System for Children-2, Parent Rating Scale-Child (BASC-2 PRS-C) in Korean children. Two study populations were recruited: a general population sample (n=2115) of 1st to 6th graders from 16 elementary schools and a clinical population (n=219) of 6-12 years old from 5 child psychiatric clinics and an epidemiological sample of autism spectrum disorder. We assessed the validity and reliability of the Korean version of BASC-2 PRS-C (K-BASC-2 PRS-C) and compared subscales with those used for US populations. Our results indicate that the K-BASC-2 PRS-C is a valuable instrument with reliability and validity for measuring developmental psychopathology that is comparable to those in Western population. However, there were some differences noted in the mean scores of BASC-2 PRS-C between Korean and US populations. K-BASC-2 PRS-C is an effective and useful instrument with psychometric properties that permits measurement of general developmental psychopathology. Observed Korean-US differences in patterns of parental reports of children's behaviors indicate the importance of the validation, standardization and cultural adaptation for tools assessing psychopathology especially when used in populations different from those for which the instrument was originally created.

  5. Dynamic analysis of Korean nuclear fuel cycle with fast reactor systems

    International Nuclear Information System (INIS)

    Jeong, Chang Joon

    2004-12-01

    The Korean nuclear fuel cycle scenario was analyzed by the dynamic analysis method, including Pressurized Water Reactor (PWR), Canadian Deuterium Uranium (CANDU) and fast reactor systems. For the once-through fuel cycle model, the existing nuclear power plant construction plan was considered up to 2016, while the nuclear demand growth rate from the year 2016 was assumed to be 1%. After setting up the once-through fuel cycle model, the Korea Advanced Liquid Metal Reactor (KALIMER) scenario was modeled to investigate the fuel cycle parameters. For the analysis of the fast reactor fuel cycle, both KAILMER-150 and KALIMER-600 reactors were considered. In this analysis, the spent fuel inventory as well as the amount of plutonium, Minor Actinides (MA) and Fission Products (FP) of the recycling fuel cycle was estimated and compared to that of the once-through fuel cycle. Results of the once-through fuel cycle calculation showed that the demand grows up to 64 GWe and total amount of spent fuel would be ∼102 kt in 2100. If the KALIMER scenario is implemented, the total spent fuel inventory can be reduced by ∼80%. However it was found that the KALIMER scenario does not contribute to reduce the amount of MA and FP, which is important when designing a repository. For the further destruction of MA, an actinide burner can be considered in the future nuclear fuel cycle

  6. Aging management strategy for reactor internals of Korean nuclear power plants

    International Nuclear Information System (INIS)

    Hwang, Seong Sik; Kim, Soung Woo; Lee, Sam Lai; Hong, Seung Mo; Kim, Hong Pyo; Kim, Dong Jin; Lim, Yun Soo; Kim, Joung Soo; Jung, Man Kyo; Park, Jang Yul

    2010-01-01

    This report describes various factors on the IASCC of reactor internals in terms of fluence, stress, water chemistries and materials. Materials of each components of Korean nuclear power plants have been surveyed. A technical report for a management of reactor internals issued by EPRI was reviewed for a selection of most susceptible area among many components. Baffle former bolts are considered to be the most susceptible parts due to high irradiation level(fluence) and high tensile stress. Neutron fluence of Kori-1 and Kori-2 was calculated based on fuel exchange history, fuel performance and plant operation history. This report will be used for more advanced inspection and maintenance guidelines development by supplying inspection intervals and components (most susceptible regions) for the long term operation plants

  7. Underestimation of Self-Reported Smoking Prevalence in Korean Adolescents: Evidence from Gold Standard by Combined Method.

    Science.gov (United States)

    Hwang, Jun Hyun; Kim, Jong Yeon; Lee, Do Hoon; Jung, Hye Gyoun; Park, Soon-Woo

    2018-04-05

    The objective of this study was to evaluate the validity of self-reported smoking prevalence in Korean adolescents by using an improved gold standard by a combined method. Using a stratified sampling method, we selected 13 schools from among 397 high schools that participated in the 2015 Korean Youth Health Risk Behavior Web-Based Survey (KYRBS). A second survey (repeated self-reporting questionnaire and urinary cotinine test) was conducted on 1058 students who completed the KYRBS. The gold standard of current smoker was defined as those either self-reporting as a smoker in the second survey or having a urinary cotinine concentration ≥50 ng/mL. The current smoking prevalence in the first survey (KYRBS) was 7.9% (boys 16.5% and girls 1.8%), which was lower than the results based on gold standard (11.3% total, boys 21.9% and girls 3.7%). The sensitivity and specificity of self-reported smoking status was 62.5% and 99.0%, respectively. In particular, the sensitivity of girls (43.5%) was lower than that of boys (67.0%). The self-reported smoking prevalence in Korean adolescents was underestimated, particularly among girls. Careful attention should be paid to interpreting adolescents' smoking prevalence, and supplementary surveys or periodic validity tests need to be considered in Asian countries.

  8. Challenges of nuclear power for the sustainable role in Korean energy policy

    International Nuclear Information System (INIS)

    Lee, Y. E.

    2007-01-01

    This study aims to introduce the current role of nuclear power of Korea as the economic and low carbon emitter in the long term expansion planning and to improve the public acceptance of nuclear as the environmentally friendliness energy source. Nuclear and coal have been selected as the major electricity sources due to the insufficient domestic energy resources, and will provide more than 60% of total electricity generation in Korea for quite some time. National energy policy addressing environmental friendliness, stable supply and least cost has made it difficult to decide which energy resource is the best for the long term energy planning. Climate change regime will diminish the coal power plants in generation amount, the public still keeps nuclear at a distance and insists to replace nuclear by renewable and renewable doesn't any guarantee of stable supply although its economics is fast being improved. Therefore, it is necessary to analyze the long-term power expansion planning in various points of view such as environmental friendliness, benefit of carbon reduction and system reliability as well as least cost operation. The objective and approach of this study are to analyze the proper role of nuclear power by comparing the different types of scenarios in terms of the system cost changes, CO 2 emission reduction and system reliability. The results from this analysis are useful for the Korean government in charge of long-term energy policy to go over what kinds of role can each electric resources play and what are the best way to solve the triangular dilemma as economics, environmental friendliness, stable supply of the electricity

  9. The current status and future prospects of the Korean nuclear power industry

    International Nuclear Information System (INIS)

    Lee, J. J.

    2006-01-01

    Recently, countries all over the world are becoming aware of the values and importance of nuclear energy which can help respond to energy crises caused by a sharp rise in oil prices and protect the earth from global warming. Since 1978, when Kori Unit 1(587MW), opened the nuclear generation era as a semi-domestic energy resource in Korea which is absolutely in short supply of energy, nuclear power generation in Korea has developed continuously for the past 28 years. Four new units including the Yonggwang 5 and 6 and Ulchin 5 and 6 have been successfully completed, raising the total nuclear installed capacity to 17,716MW from 20 units. At present, the nuclear generation in Korea is stably supplying about 40% of total electric generation, which is the fundamental energy of the nation, supporting the dynamic economic growth of Korea. In particular, Korean nuclear industry has been achieving excellent performance in nuclear power plant operation. The average capacity factor in 2005 hit the record of 95.5%, surpassing the previous record of 94.2% in 2003 in two years. Kori Unit 4 and another four units were listed at the top five in the capacity factor rating list of 2005 released by Nucleonics Week. In 2005, the site for radioactive waste disposal, which had been a long-cherished hope and the largest pending issue of the nuclear industry, was successfully selected in Korea through resident ballot as the first case of a national policy project, and as such, a national agenda was solved after 19 long years. Such a method in site selection has a significant meaning and establishes an excellent precedence; a large national policy project was decided upon by the residents themselves. As one of the model countries of building and operating nuclear power plants and technological independence, Korea is willing to contribute to the common goals of the world nuclear circle which can be summarized into energy security and environment preservation, by sharing accumulated

  10. Globalization of ASME Nuclear Codes and Standards

    International Nuclear Information System (INIS)

    Swayne, Rick; Erler, Bryan A.

    2006-01-01

    With the globalization of the nuclear industry, it is clear that the reactor suppliers are based in many countries around the world (such as United States, France, Japan, Canada, South Korea, South Africa) and they will be marketing their reactors to many countries around the world (such as US, China, South Korea, France, Canada, Finland, Taiwan). They will also be fabricating their components in many different countries around the world. With this situation, it is clear that the requirements of ASME Nuclear Codes and Standards need to be adjusted to accommodate the regulations, fabricating processes, and technology of various countries around the world. It is also very important for the American Society of Mechanical Engineers (ASME) to be able to assure that products meeting the applicable ASME Code requirements will provide the same level of safety and quality assurance as those products currently fabricated under the ASME accreditation process. To do this, many countries are in the process of establishing or changing their regulations, and it is important for ASME to interface with the appropriate organizations in those countries, in order to ensure there is effective use of ASME Codes and standards around the world. (authors)

  11. Materials integrity analysis for application of POSCO developed STS to Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Hyun-Young, Ch.; Tae-Eun, J.; Young-Sik, K.

    2009-01-01

    Full text of publication follows: POSCO has developed duplex stainless steel (S32750) and hyper super duplex stainless steels for the purpose of using them in the secondary circulation cooling water system in Korean nuclear power plants. This system supplies seawater to cooling water heat exchanger tubes, related pipes and chlorine injection system. In normal operation, seawater is supplied to heat exchanger through the exit of circulation pump headers and the heat exchanged sea water is extracted to the discharge pipes in circulation cooling water system connected to the circulation water discharge lines. The flow velocity of circulation cooling water system in nuclear power plants is high and damages of components from corrosion are severe. Therefore, this environment makes requiring of using high strength and high corrosion resistant steels. Hyper duplex stainless steel (27Cr-7.0Ni-2.5Mo-3.2W-0.35N) has been newly developed in Korea and is being improved for applying to nuclear power plants. In this study, the physical and mechanical properties and corrosion resistance of currently producing stainless steels and newly developed materials are qualitatively evaluated in comparative to commercial stainless steels in other countries. The properties of weld are analyzed and the best compositions of welding rod are suggested. The optimum weld condition is derived for ensuring HAZ phase ratios and controlling weld cracks. For applying these materials to the seawater heat exchanger, CCT and CPT in weldments are measured using mock-up tube testers that are newly designed for this study. Coupons of candidate materials are introduced in the real system and corrosion resistance of them are analyzed. As results of all experiments, the current CCT and CPT criteria in Korean nuclear power plants are reviewed, and the more actual and strengthened criteria will be suggested. The real scale components made of newly developed hyper super duplex stainless steel will be applied to

  12. Seismic design standardization of nuclear facilities

    International Nuclear Information System (INIS)

    Reddy, G.R.; Vaze, K.K.

    2011-01-01

    Full text: Structures, Systems and Components (SSCs) of Nuclear Facilities have to be designed for normal operating loads such as dead weight, pressure, temperature etc., and accidental loads such as earthquakes, floods, extreme, wind air craft impact, explosions etc. Man made accidents such as aircraft impact, explosions etc., some times may be considered as design basis event and some times taken care by providing administrative controls. This will not be possible in the case of natural events such as earthquakes, flooding, extreme winds etc. Among natural events earthquakes are considered as most devastating and need to be considered as design basis event. It is generally felt design of SSCs for earthquake loads is very time consuming and expensive. Conventional seismic design approaches demands for large number of supports for systems and components. This results in large space occupation and in turn creates difficulties for maintenance and in service inspection of systems and components. In addition, complete exercise of design need to be repeated for plants being located at different sites due to different seismic demands. However, advanced seismic response control methods will help to standardize the seismic design meeting the safety and economy. These methods adopt passive, semi active and active devices, and base isolators to control the seismic response. In nuclear industry, it is advisable to go for passive devices to control the seismic responses. Ideally speaking, these methods will make the designs made for normal loads can also satisfy the seismic demand without calling for change in material, geometry, layout etc. in the SSCs. This paper explain the basic ideas of seismic response control methods, demonstrate the effectiveness of control methods through case studies and eventually give the procedure to be adopted for seismic design standardization of nuclear facilities

  13. Change in Knowledge of Korean Elementary, Middle, and High School Students in the Fundamental Education on the Nuclear Power Generation

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jaerok; Lee, Seungkoo; Choi, Yoonseok; Han, Eunok [Korea Academy of Nuclear Safety, Seoul (Korea, Republic of)

    2014-05-15

    Nuclear power facilities and policies are based upon their acceptability to local residents and citizens. In Korea, where nuclear power should be consistently used for national energy security and economic growth, it is important to enhance the social acceptability of nuclear power. To do so, it is necessary to relieve the minds of the Korean people and global nuclear power communities regarding safety. However, there is sharp division on the perception of nuclear power safety between the expert group of operators, philosophers, and regulators, and ordinary citizens, local residents, media, and anti-nuclear groups. This study designed an experiment on knowledge change as part of an educational strategy to enhance public understanding and develop extensive bonds of sympathy for nuclear power generation adequate for Korean society. In order to provide fundamental evidence for planning an educational intervention strategy, this study analyzed the knowledge change of elementary, middle, and high school students, who are then expected to impact education of the general population. As a result of conducting a 45 minute-long education on the principles, state of use, advantages, and disadvantages of nuclear power generation for Korean elementary, middle, and high school students, the levels of objective knowledge (p<0.000) was significantly higher. This indicates that if education for enhancing social acceptance in Korea argued nuclear power should be constantly used, an education effect could be anticipated. Although objective knowledge does not have any direct influence on behavior change, it is an important variable for attitude change, and thus information on objective knowledge should be offered as well. Here, the contents preferred by the education subjects should also be considered.

  14. Change in Knowledge of Korean Elementary, Middle, and High School Students in the Fundamental Education on the Nuclear Power Generation

    International Nuclear Information System (INIS)

    Kim, Jaerok; Lee, Seungkoo; Choi, Yoonseok; Han, Eunok

    2014-01-01

    Nuclear power facilities and policies are based upon their acceptability to local residents and citizens. In Korea, where nuclear power should be consistently used for national energy security and economic growth, it is important to enhance the social acceptability of nuclear power. To do so, it is necessary to relieve the minds of the Korean people and global nuclear power communities regarding safety. However, there is sharp division on the perception of nuclear power safety between the expert group of operators, philosophers, and regulators, and ordinary citizens, local residents, media, and anti-nuclear groups. This study designed an experiment on knowledge change as part of an educational strategy to enhance public understanding and develop extensive bonds of sympathy for nuclear power generation adequate for Korean society. In order to provide fundamental evidence for planning an educational intervention strategy, this study analyzed the knowledge change of elementary, middle, and high school students, who are then expected to impact education of the general population. As a result of conducting a 45 minute-long education on the principles, state of use, advantages, and disadvantages of nuclear power generation for Korean elementary, middle, and high school students, the levels of objective knowledge (p<0.000) was significantly higher. This indicates that if education for enhancing social acceptance in Korea argued nuclear power should be constantly used, an education effect could be anticipated. Although objective knowledge does not have any direct influence on behavior change, it is an important variable for attitude change, and thus information on objective knowledge should be offered as well. Here, the contents preferred by the education subjects should also be considered

  15. Standardization of Nuclear Instrumentation Applied in the NPP and in other nuclear installations

    International Nuclear Information System (INIS)

    Kusnowo, Arlinah; Darmawati, Suzie

    2002-01-01

    Nuclear power plant (NPP) and other nuclear installations have been recognized as applications needing very sophisticated technologies. One of technologies used in this all nuclear facilities is nuclear instrumentation. In order that NPP and other nuclear installations be operated safely, nuclear instrumentation requires standardization from design to its operation. Internationally, standardizations of nuclear instrumentation have been issued by IEC (International Electrotechnical Commission). Formulation of standard in nuclear instrumentation in IEC is carried out by Technical Committee (TC) 45. This paper describes briefly the standardization of nuclear instrumentation applied in Indonesia as Indonesian National Standard (SNI, Standard National Indonesia), standardization of nuclear instrumentation developed by TC 45, SC 45A, and SC 45B, as well as the possibility to adopt and apply those IEC standard in Indonesia

  16. A Study on the Job Stress Assessment in Korean Nuclear Power Plants based on KOSS

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Seong Hwan; Lee, Yong Hee; Lee, Jung Woon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Sung, Sook Hee; Jung, Kwang Hee; Jung, Yeon Sub [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2010-05-15

    Job stress is a harmful physical and emotional response that occurs when there is a poor match between job demands and the capabilities, resources, or needs of the worker. Stress-related disorders encompass a broad array of conditions, including psychological disorders (e.g., depression, anxiety, posttraumatic stress disorder) and other types of emotional strain (e.g., dissatisfaction, fatigue, tension, etc.), maladaptive behaviors (e.g., aggression, substance abuse), and cognitive impairment (e.g., concentration and memory problems). In turn, these conditions may lead to poor work performance or even injury. Job stress is also associated with various biological reactions that may lead ultimately to compromised health, such as cardiovascular disease or in extreme cases, death. In Korea, organizational job stress factors were investigated for the jobs in nuclear power plants that are operated based on procedures. Especially, the occupational stress scale for Korean employees (KOSS) was developed. The KOSS has 8 subscales by using a factor analysis and validation process in order to measure stress at work and to find methods for the prevention of stressors. In this point of view, the RHRI (Radiation Health Research Institute of KHNP (Korea Hydro and Nuclear Power) assessed how wellsuited employees were for their job during their health examination in 2009. In this study the present condition of employee's stress level is investigated to find a way to manage their stressors

  17. A Study on the Job Stress Assessment in Korean Nuclear Power Plants based on KOSS

    International Nuclear Information System (INIS)

    Hwang, Seong Hwan; Lee, Yong Hee; Lee, Jung Woon; Sung, Sook Hee; Jung, Kwang Hee; Jung, Yeon Sub

    2010-01-01

    Job stress is a harmful physical and emotional response that occurs when there is a poor match between job demands and the capabilities, resources, or needs of the worker. Stress-related disorders encompass a broad array of conditions, including psychological disorders (e.g., depression, anxiety, posttraumatic stress disorder) and other types of emotional strain (e.g., dissatisfaction, fatigue, tension, etc.), maladaptive behaviors (e.g., aggression, substance abuse), and cognitive impairment (e.g., concentration and memory problems). In turn, these conditions may lead to poor work performance or even injury. Job stress is also associated with various biological reactions that may lead ultimately to compromised health, such as cardiovascular disease or in extreme cases, death. In Korea, organizational job stress factors were investigated for the jobs in nuclear power plants that are operated based on procedures. Especially, the occupational stress scale for Korean employees (KOSS) was developed. The KOSS has 8 subscales by using a factor analysis and validation process in order to measure stress at work and to find methods for the prevention of stressors. In this point of view, the RHRI (Radiation Health Research Institute of KHNP (Korea Hydro and Nuclear Power) assessed how wellsuited employees were for their job during their health examination in 2009. In this study the present condition of employee's stress level is investigated to find a way to manage their stressors

  18. Statistical analysis on the fluence factor of surveillance test data of Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Gyeong Geun; Kim, Min Chul; Yoon, Ji Hyun; Lee, Bong Sang; Lim, Sang Yeob; Kwon, Jun Hyun [Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2017-06-15

    The transition temperature shift (TTS) of the reactor pressure vessel materials is an important factor that determines the lifetime of a nuclear power plant. The prediction of the TTS at the end of a plant’s lifespan is calculated based on the equation of Regulatory Guide 1.99 revision 2 (RG1.99/2) from the US. The fluence factor in the equation was expressed as a power function, and the exponent value was determined by the early surveillance data in the US. Recently, an advanced approach to estimate the TTS was proposed in various countries for nuclear power plants, and Korea is considering the development of a new TTS model. In this study, the TTS trend of the Korean surveillance test results was analyzed using a nonlinear regression model and a mixed-effect model based on the power function. The nonlinear regression model yielded a similar exponent as the power function in the fluence compared with RG1.99/2. The mixed-effect model had a higher value of the exponent and showed superior goodness of fit compared with the nonlinear regression model. Compared with RG1.99/2 and RG1.99/3, the mixed-effect model provided a more accurate prediction of the TTS.

  19. Korean experience on the development and deployment of nuclear power plants

    International Nuclear Information System (INIS)

    2009-01-01

    The primary objective of the Republic of Korea's energy policy has been to secure an economical and stable supply of energy by diversifying energy sources. At present, environment-friendly energy policies have gained ground due largely to a progress in climate change convention negotiations. The impact of the two oil crises in the 1970s on the Korean economy was severe. In response, the government tried to limit the annual increase in energy consumption to about 7∼8%. By the 1990s, however, consumption was growing at more than 10% annually. The total primary energy consumption increased from 12.0 million TOE in 1965 to 233.4 million TOE in 2006. Due to the scarcity of indigenous energy resources, the Republic of Korea is heavily dependent upon imported energy. The overseas energy dependence continuously rises from 47.5% in 1970 to 96.5% in 2006. As in many other countries that are not endowed with fossil fuel reserves, nuclear power is considered to be the most reliable energy source capable of meeting the soaring energy demand necessary for economic development (i.e. an economic growth rate of some 10% per year). The Republic of Korea has consequently chosen nuclear power as one of its major energy sources

  20. Strategic plan for the development of core technologies for the Korean advanced nuclear power reactor for export

    International Nuclear Information System (INIS)

    Moon, Joo Hyun; Cho, Young Ho

    2010-01-01

    With the soaring oil price and worsening global warming, nuclear power has attracted considerable attention on a global scale and a new large market of nuclear power plants (NPPs) is expected. The Korean government aims to export up to 10 NPPs by 2012, based on the successful export of 2 NPPs to the UAE in 2009. It is also going to develop a follow-up model of the Advanced Power Reactor (APR) 1400, and join the world's NPP market under the banner of Korea's original reactor type. For this, it promulgated the strategic plan, NuTech 2012, a technology development plan intended for the early acquisition of core technologies for the Korean advanced NPP design and domestic production of the main components in NPP. This paper introduces the strategic plan of NuTech 2012. (orig.)

  1. Standardized analyses of nuclear shipping containers

    International Nuclear Information System (INIS)

    Parks, C.V.; Hermann, O.W.; Petrie, L.M.; Hoffman, T.J.; Tang, J.S.; Landers, N.F.; Turner, W.D.

    1983-01-01

    This paper describes improved capabilities for analyses of nuclear fuel shipping containers within SCALE -- a modular code system for Standardized Computer Analyses for Licensing Evaluation. Criticality analysis improvements include the new KENO V, a code which contains an enhanced geometry package and a new control module which uses KENO V and allows a criticality search on optimum pitch (maximum k-effective) to be performed. The SAS2 sequence is a new shielding analysis module which couples fuel burnup, source term generation, and radial cask shielding. The SAS5 shielding sequence allows a multidimensional Monte Carlo analysis of a shipping cask with code generated biasing of the particle histories. The thermal analysis sequence (HTAS1) provides an easy-to-use tool for evaluating a shipping cask response to the accident capability of the SCALE system to provide the cask designer or evaluator with a computational system that provides the automated procedures and easy-to-understand input that leads to standarization

  2. Development of nuclear power standards and relevant system in China

    International Nuclear Information System (INIS)

    Cao Shudong

    2008-01-01

    By analyzing the history of nuclear power development and the status of nuclear power codes and standards in China, the significance and necessity to quicken the development of nuclear power standards system in China are pointed out, and the guiding ideology, development thoughts, working doctrine and development objectives are put forward in this paper. (authors)

  3. Four Kilograms to Tip the Scale: China’s Exploitation of the North Korean Nuclear Crisis

    Science.gov (United States)

    2007-12-01

    for power in East Asia. There is only ever one hegemon in the region at a time - “One mountain cannot accommodate two tigers .”35 China was the...Pyongyang by Washington 148 “Japan Downgraded With 29-year-old Woman Named Director For Asian Affairs at White ...the North Korean crisis active. Linking the Trans-Korean Railway (TKR) with the Trans- Siberian Railway (TSR) offers faster routes for Korean goods

  4. Accelerating nuclear power standards development and promoting sound nuclear power development in China

    International Nuclear Information System (INIS)

    Yang Changli

    2008-01-01

    The paper expounds the importance of quickening establishment and perfection of nuclear power standard system in China, analyzes achievements made and problems existed during the development of nuclear power standards, put forward proposals to actively promote the work in this regard, and indicates that CNNC will further strengthen the standardization work, enhance coordination with those trades related to nuclear power standards, and jointly promote the development of nuclear power standards. (authors)

  5. Thermal safety analysis of a dry storage cask for the Korean standard spent fuel - 16159

    International Nuclear Information System (INIS)

    Cha, Jeonghun; Kim, S.N.; Choi, K.W.

    2009-01-01

    A conceptual dry storage facility, which is based on a commercial dry storage facility, was designed for the Korea standard spent nuclear fuel (SNF) and preliminary thermal safety analysis was performed in this study. To perform the preliminary thermal analysis, a thermal analysis method was proposed. The thermal analysis method consists of 2 parts. By using the method, the surface temperature of the storage canister corresponding to the SNF clad temperature was calculated and the adequate air duct area was decided using the calculation result. The initial temperature of the facility was calculated and the fire condition and half air duct blockage were analyzed. (authors)

  6. Social networking-based simulations for nuclear security: Strategy assessment following nuclear cyber terror on South Korean nuclear power plants (NPPs)

    International Nuclear Information System (INIS)

    Woo, Tae Ho; Kwak, Sang Man

    2015-01-01

    Highlights: • The cyber terror modeling is made by the social networking algorithm. • This is applicable by the social networking service (SNS). • Security of nuclear industry could be controlled by the network theory. • Newly developed complex algorithm can be introduced. • Simplified graphics show the operator easily. - Abstract: Nuclear energy has been studied for the secure power productions, which is based on the simulation study following the incident of nuclear cyber terror attack on South Korean nuclear power plants (NPPs). The social networking is used for the terror incident modeling and its prevention strategies. The nuclear industry could be investigated in the aspect of minimizing the dangerous situations caused by possible terror attacks which are considered by the society oriented connectivity among the related people or groups. The social networking circle by system dynamics diagram (SNCSD) is constructed, where the configuration of a model social networking example by system dynamics (SD) is applied. From A to H regions, the values are obtained by the random numbers incorporated with the designed algorithms. The results show the comparative values of terror possibilities which are based on the proposed social networking algorithm. It is possible to prepare for potential terrorism in the nuclear industry

  7. Application of flow-controllable accumulator and performance analysis in Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Jung, Byung-Ryul; Lee, Un-Chul

    1997-01-01

    The Korean Yonggwang Nuclear Power Plants 3 ampersand 4(YGN 3 ampersand 4) are the two-loop pressurized water reactor (PWR) nuclear steam supply systems, rated at 2,815 MW(thermal). They incorporate the safety injection system (SIS) consisting of the two high pressure (HPSI) pumps, two low pressure safety injection (LPSI) pumps, and four accumulators. The SIS is two headered arrangements, each to four cold legs injection (CLI) type which provides cooling to the core in the highly unlikely event of a loss-of-coolant accident (LOCA). In the current SIS, the LPSI pumps automatically start during a LOCA, and also provide the residual heat removal capability during the shutdown cooling. This paper presents the feasibility of the removal of the LPSI from the existing SIS with minor system changes, including the increase up to four in the HPSI pumps, direct vessel injection(DVI), and the flow-controllable accumulators. A double-ended rupture of one of the four cold legs in the YGN 3 ampersand 4 was simulated using RELAP5/MOD3.1 to determine the feasibility of the application of this new SIS design to the current nuclear power plants. As a result, the calculated reflooding peak cladding surface temperature(PCT) was comparable to that of original base calculation, and the downcomer and the core collapsed liquid level during reflooding were also comparable to those in the current safety system design. This large break, cold-leg LOCA analysis addresses the reflooding capability without credit for a LPSI pump system and the applicability of the new flow-controllable accumulator. Also this analysis confirms that the combination of new flow-controllable accumulators, DVI and the increased HPSI pumps maintain the peak cladding temperature below the prescribed limits. 14 refs., 4 figs., 3 tabs

  8. Brief overview of American Nuclear Society's research reactor standards

    International Nuclear Information System (INIS)

    Richards, Wade J.

    1984-01-01

    The American Nuclear Society (ANS) established the research reactor standards group in 1968. The standards group, known as ANS-15, was established for the purpose of developing, preparing, and maintaining standards for the design, construction, operation, maintenance, and decommissioning of nuclear reactors intended for research and training

  9. Traveling ionospheric disturbances triggered by the 2009 North Korean underground nuclear explosion

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, X.; Tang, L. [Wuhan Univ. (China). School of Geodesy and Geomatics

    2015-04-01

    Underground nuclear explosions (UNEs) can induce acoustic-gravity waves, which disturb the ionosphere and initiate traveling ionospheric disturbances (TIDs). In this paper, we employ a multi-step and multi-order numerical difference method with dual-frequency GPS data to detect ionospheric disturbances triggered by the North Korean UNE on 25 May 2009. Several International GNSS Service (IGS) stations with different distances (400 to 1200 km) from the epicenter were chosen for the experiment. The results show that there are two types of disturbances in the ionospheric disturbance series: high-frequency TIDs with periods of approximately 1 to 2 min and low-frequency waves with period spectrums of 2 to 5 min. The observed TIDs are situated around the epicenter of the UNE, and show similar features, indicating the origin of the observed disturbances is the UNE event. According to the amplitudes, periods and average propagation velocities, the high-frequency and low-frequency TIDs can be attributed to the acoustic waves in the lower ionosphere and higher ionosphere, respectively. (orig.)

  10. Complete analysis of a nuclear building to nuclear safety standards

    Energy Technology Data Exchange (ETDEWEB)

    Jaeger, T A

    1975-01-01

    The nuclear standards impose on the designer the necessity of examining the loads, stresses, and strains in a nuclear building even under extreme loading conditions, both due to plant malfunctions and environmental accidents. It is necessary then to generate, combine, and examine a tremendous amount of data; really the lack of symmetry and general complication of the structures and the large number of loading combinations make an automatic analysis quite necessary. A largely automated procedure is presented in view of solving the problem by a series of computer programs linked together. After the seismic analysis has been performed by (SADE CODE) these data together with the data coming from thermal specifications, weight, accident descriptions etc. are fed into a finite element computer code (SAP4) for analysis. They are processed and combined by a computer code (COMBIN) according to the loading conditions (the usual list in Italy is given and briefly discussed), so that for each point (or each selected zone) under each loading condition the applied loads are listed. These data are fed to another computer code (DTP), which determines the amount of reinforcing bars necessary to accommodate the most severe of the loading conditions. The Aci 318/71 and Italian regulation procedures are followed; the characteristics of the program are briefly described and discussed. Some particular problems are discussed, e.g. the thermal stresses due to normal and accident conditions, the inelastic behavior of some frame elements (due to concrete cracking) is considered by means of an 'ad hoc' code. Typical examples are presented and the results are discussed showing a relatively large benefit in considering this inelastic effect.

  11. Development of an accident consequence assessment code for evaluating site suitability of light- and heavy-water reactors based on the Korean Technical standards

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Won Tae; Jeong, Hae Sung; Jeong, Hyo Joon; Kil, A Reum; Kim, Eun Han; Han, Moon Hee [Nuclear Environment Safety Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-12-15

    Methodologies for a series of radiological consequence assessments show a distinctive difference according to the design principles of the original nuclear suppliers and their technical standards to be imposed. This is due to the uncertainties of the accidental source term, radionuclide behavior in the environment, and subsequent radiological dose. Both types of PWR and PHWR are operated in Korea. However, technical standards for evaluating atmospheric dispersion have been enacted based on the U.S. NRC's positions regardless of the reactor types. For this reason, it might cause a controversy between the licensor and licensee of a nuclear power plant. It was modelled under the framework of the NRC Regulatory Guide 1.145 for light-water reactors, reflecting the features of heavy-water reactors as specified in the Canadian National Standard and the modelling features in MACCS2, such as atmospheric diffusion coefficient, ground deposition, surface roughness, radioactive plume depletion, and exposure from ground deposition. An integrated accident consequence assessment code, ACCESS (Accident Consequence Assessment Code for Evaluating Site Suitability), was developed by taking into account the unique regulatory positions for reactor types under the framework of the current Korean technical standards. Field tracer experiments and hand calculations have been carried out for validation and verification of the models. The modelling approaches of ACCESS and its features are introduced, and its applicative results for a hypothetical accidental scenario are comprehensively discussed. In an applicative study, the predicted results by the light-water reactor assessment model were higher than those by other models in terms of total doses.

  12. Korea nuclear exports: Why did the Koreans win the UAE tender? Will Korea achieve its goal of exporting 80 nuclear reactors by 2030?

    International Nuclear Information System (INIS)

    Berthelemy, Michel; Leveque, Francois

    2011-01-01

    The success of Korea in winning, in December 2009, a USD 18.6 billion nuclear tender in the United Arab Emirates (UAE) has led to a growing interest in the organization and strengths of the Korean nuclear industry. In this paper, we present the main economic and political factors that explain the success of the Korean consortium. In particular, thanks to an active national program of Nuclear Power Plant (NPP) construction, Korea has developed distinct competitive advantages in terms of low cost, high credibility and high performance. At the same time, due to the important barriers to enter into the nuclear export market in the UAE, Korea has had to sacrifice its profit margin and has benefited from a strong political support from its government through export financing. More importantly, Korea's success is also due to its alliance with Westinghouse and the support of the US diplomacy. Subsequently, we show that while Korea has recently experienced setbacks in nuclear tenders, it will most certainly try to win in the short run a second nuclear tender with another aggressive price. In the longer run, Korea could take a growing share of the international market for NPPs. However, the extent to which Korea can achieve its long term export target will depend upon its capacity to finance nuclear export through export credits and upon the development of its alliance with Westinghouse. It is important to note that this paper was written before the Fukushima nuclear disaster. The scale of the human and environmental consequences of this accident are still unknown, and will undoubtedly have short and long term consequences on nuclear safety requirements and public attitude toward nuclear energy, which will most certainly impact the outlooks for nuclear new-builds. (authors)

  13. The north-Korean nuclear program. Round table. What do we know? What do we think we know? And what are the resulting actions?

    International Nuclear Information System (INIS)

    Pollack, J.

    2004-06-01

    The North-Korean nuclear program is problematic because of the specific government policy from which information are coming with difficulty. From open sources, the author takes stock on our knowledge concerning the military nuclear program of Pyongyang by looking on the two possible channels of nuclear matter production for nuclear weapons and on the weapons construction. He concludes on the actions to realize facing the uncertainties. (A.L.B.)

  14. Safety standards and safety record of nuclear power plants

    International Nuclear Information System (INIS)

    Davis, A.B.

    1984-01-01

    This paper focuses on the use of standards and the measurement and enforcement of these standards to achieve safe operation of nuclear power plants. Since a discussion of the safety standards that the Nuclear Regulatory Commission (NRC) uses to regulate the nuclear power industry can be a rather tedious subject, this discussion will provide you with not only a description of what safety standards are, but some examples of their application, and various indicators that provide an overall perspective on safety. These remarks are confined to the safety standards adopted by the NRC. There are other agencies such as the Environmental Protection Agency, the Occupational Safety and Health Administration, and the state regulatory agencies which impact on a nuclear power plant. The NRC has regulatory authority for the commercial use of the nuclear materials and facilities which are defined in the Atomic Energy Act of 1954 to assure that the public health and safety and national security are protected

  15. Nuclear powerplant standardization: light water reactors. Volume 2. Appendixes

    International Nuclear Information System (INIS)

    1981-06-01

    This volume contains working papers written for OTA to assist in preparation of the report, NUCLEAR POWERPLANT STANDARDIZATION: LIGHT WATER REACTORS. Included in the appendixes are the following: the current state of standardization, an application of the principles of the Naval Reactors Program to commercial reactors; the NRC and standardization, impacts of nuclear powerplant standardization on public health and safety, descriptions of current control room designs and Duke Power's letter, Admiral Rickover's testimony, a history of standardization in the NRC, and details on the impact of standardization on public health and safety

  16. Development of Emergency Operating Strategies for Beyond Design Basis External Event(BDBEE)s in Korean WH Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Duk-Joo; Lee, Seung-Chan; Sung, Je-Joong; Ha, Sang-Jun [KHNP CRI, Daejeon (Korea, Republic of); Hong, Soon-Joon; Hwang, Su-Hyun; Lee, Byung-Chul; Park, Kang-Min [FNC Tech. Co., Yongin (Korea, Republic of)

    2015-10-15

    Westinghouse developed and connected emergency operating procedures into a set of FLEX Support Guidelines(FSGs). This paper explains that Korean WH(Westinghouse) type nuclear power plants develop emergency operating strategies for ELAP(extended loss of all AC power), which include guidelines to use permanent and portable equipment as necessary to prevent core damage until AC power is restored from a reliable alternate source of AC power. The Korean emergency operating response strategies were developed to cope with a ELAP such as Fukushima event. The strategies include guidelines to prevent fuel damage using the FLEX equipment. Operators should take actions to prepare FLEX equipment within license basis SBO coping time. The loss of all AC power has been analyzed to identify the behavior of major NSSS process variables using RELAP computer code. The accident analysis showed that the plant does not result in fuel damage in 72 hours after an ELAP if operators take actions to cool RCS with opening of SG ADV in 5 gpm seal leak case. In this scenario, because ELAP is in process and all power cannot be used, operator should operate the FLEX equipment in order to actuate active equipment using the EOP fo SBO response. This strategy will prevent entering SAMG because this actions result in core cooling and stay in core exit temperature less than 650 .deg. C. Korean emergency operating guidelines(EOGs) will be developed using this strategies for response to the BDBEE.

  17. Proprietary, standard, and government-supported nuclear data bases

    International Nuclear Information System (INIS)

    Poncelet, C.G.; Ozer, O.; Harris, D.R.

    1975-07-01

    This study presents an assessment of the complex situation surrounding nuclear data bases for nuclear power technology. Requirements for nuclear data bases are identified as regards engineering functions and system applications for the many and various user groups that rely on nuclear data bases. Current practices in the development and generation of nuclear data sets are described, and the competitive aspect of design nuclear data set development is noted. The past and current role of the federal government in nuclear data base development is reviewed, and the relative merits of continued government involvement are explored. National policies of the United States and other industrial countries regarding the availability of nationally supported nuclear data information are reviewed. Current proprietary policies of reactor vendors regarding design library data sets are discussed along with the basis for such proprietary policies. The legal aspects of protective policies are explored as are their impacts on the nuclear power industry as a whole. The effect of the regulatory process on the availability and documentation of nuclear data bases is examined. Current nuclear data standard developments are reviewed, including a discussion of the standard preparation process. Standards currently proposed or in preparation that directly relate to nuclear data bases are discussed in some detail. (auth)

  18. A cytogenetic study of Korean native goat bred in the nuclear power plant using the micronucleus assay

    International Nuclear Information System (INIS)

    Kang, Chang-Mo; Ji, Young-Hoon; Lee, Hae-June; Kim, Se-Ra; Kim, Jong-Choon; Kim, Sung-Ho

    2005-01-01

    Cytogenetic and hematological analysis was performed on the peripheral blood lymphocytes (PBLs) obtained from Korean native goats bred in two nuclear power plants (Wolsong and Uljin) and a control area. The frequencies of gamma-ray-induced micronuclei (MN) in the cytokinesis-blocked (CB) lymphocytes at several doses were measured in three Korean native goats. The measurements performed after irradiation showed dose-related increases in the MN frequency in each of the donors. The results were analyzed using a linear-quadratic model with a line of best fit of y=0.1019D+0.0045D 2 +0.0093 (y=number of MN/GB cells and D=irradiation dose in Gy). The MN rates in the goats from the Wolsong and Uljin nuclear power plant, and the control area were 9.60±2.88, 6.83±1.47 and 9.88±4.32 per 1,000 CB lymphocytes, respectively. The apparent difference is not statistically significant. The MN frequencies of PBLs from goats bred in three areas means that the values are within the background variation in this experiment. The MN frequencies and hematological values were similar regardless of whether the goats were bred in the nuclear power plant or the control area. (author)

  19. The latest trend of nuclear standards

    International Nuclear Information System (INIS)

    Tobioka, Toshiaki

    2000-01-01

    In Japan, the Atomic Energy Fundamental Law is enacted as a fundamental law on application of atomic energy. According to provision of the Law, various regulations essential to prevent national disaster, to protect nuclear substances and to secure public safety are carried out. From a viewpoint of disaster prevention, 'the Law on Regulation of Nuclear Raw Materials, Nuclear Fuel Substances and Nuclear Reactors' is enacted for its main law. On countermeasure to an emergency of accident formation at a nuclear facility, 'the Disaster Countermeasure Fundamental Law' is enacted as a general law for disaster countermeasure and defined obligation, organization, and so on of government, local community, and so on for the disaster containing large scale natural disaster, and recently 'the Nuclear Disaster Special Measure Act' was enacted by receiving necessity of enforced cooperation between government and local community. However, for a general tendency, these regulation rules and now transferring from the conventional system where a means to establish an object in safety is regulated in a meaning to a form required to finish a concrete safe target. (G.K.)

  20. Development of radiation shielding standards in the American Nuclear Society

    International Nuclear Information System (INIS)

    Trubey, D.K.

    1975-11-01

    The American Nuclear Society (ANS) is a standards-writing organization-member of the American National Standards Institute (ANSI). The ANS Standards Committee has a subcommittee denoted ANS-6, Shielding, whose charge is to establish standards in connection with radiation protection and shielding, to provide shielding information to other standards writing groups, and to prepare recommended sets of shielding data and test problems. This paper is a progress report of this subcommittee

  1. Development of EDG Engine Condition Diagnosis Logic in Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Byoung Oh; Choi, Kwang Hee; Lee, Sang Guk

    2012-01-01

    Through benchmarking using the excellent record of the nuclear power plants under operation in the United States and Europe and with the continuous development of nuclear-related technology, the Korea Hydro and Nuclear Power Co., LTD (KHNP) reached an average planned preventive maintenance period of 29.6 days in 2009. In addition, KHNP plans to reduce the planned preventive maintenance period at Korea standard nuclear plants (KSNPs) from 29.6 days to less than 21 days by 2014 through a combination of domestic research and development (R and D) and the introduction of the technical know-how applied in the very best overseas nuclear power plants (NPPs). Accordingly, it is necessary to reduce the inspection and maintenance periods of an emergency diesel generator (EDG), which are currently set in the planned preventive maintenance period. If the condition-based predictive maintenance (CBM) technology is applied to EDG engines, the maintenance period of an EDG will be shortened because engine maintenance is accomplished according to the engine condition under this plan. In this study, in the series of CBM program developments which will be applied to EDG engines, the development results of condition diagnosis logic to be applied to EDG engines for exiting domestic NPPs are introduced

  2. Progress in standards for nuclear air and gas treatment

    International Nuclear Information System (INIS)

    Burchsted, C.A.

    1978-01-01

    Standardization in nuclear air and gas treatment spans a period of more than 25 years, starting with military specifications for HEPA filters and filter media, and now progressing to the development of a formal code analogous to the ASME Boiler and Pressure Vessel Code. Whereas the current standard for components and installation of nuclear air cleaning systems is limited to safety related facilities for nuclear power plants, the proposed code will cover all types of critical ventilation and air and gas treatment installations for all types of nuclear facilities

  3. Nuclear Data Center International Standard Towards TSO Initiative

    International Nuclear Information System (INIS)

    Raja Murzaferi Raja Moktar; Mohd Fauzi Haris; Siti Nurbahyah Hamdan

    2011-01-01

    Nuclear Data Center is the main facility for Nuclear Malaysia Agency IT infrastructure comprising of main critical servers, research and operational data storage, HPC-clusters system and vital network core equipment. In recent years, international body such as TIA-Telecommunication Industry Association and Up time Institute have came out with proper international data center standards in order to ensure data center operation on achieving maximum operational up time and minimal downtime. The standard are currently being rated as tier level ranging from Data Center tier I up to tier IV, differentiate by facility standard and up time/ downtime percentage ratio. This paper will discuss Nuclear Data Center adopting international standards in supporting Nuclear Malaysia TSO initiative thus ensuring the critical core component of agency IT services availability and further more International standard recognitions. (author)

  4. The role of nuclear energy for Korean long-term energy supply strategy : application of energy demand-supply model

    International Nuclear Information System (INIS)

    Chae, Kyu Nam

    1995-02-01

    An energy demand and supply analysis is carried out to establish the future nuclear energy system of Korea in the situation of environmental restriction and resource depletion. Based on the useful energy intensity concept, a long-term energy demand forecasting model FIN2USE is developed to integrate with a supply model. The energy supply optimization model MESSAGE is improved to evaluate the role of nuclear energy system in Korean long-term energy supply strategy. Long-term demand for useful energy used as an exogeneous input of the energy supply model is derived from the trend of useful energy intensity by sectors and energy carriers. Supply-side optimization is performed for the overall energy system linked with the reactor and nuclear fuel cycle strategy. The limitation of fossil fuel resources and the CO 2 emission constraints are reflected as determinants of the future energy system. As a result of optimization of energy system using linear programming with the objective of total discounted system cost, the optimal energy system is obtained with detailed results on the nuclear sector for various scenarios. It is shown that the relative importance of nuclear energy would increase especially in the cases of CO 2 emission constraint. It is concluded that nuclear reactor strategy and fuel cycle strategy should be incorporated with national energy strategy and be changed according to environmental restriction and energy demand scenarios. It is shown that this modelling approach is suitable for a decision support system of nuclear energy policy

  5. Working out the standards for nuclear power aging management implementation (PLM Standards)

    International Nuclear Information System (INIS)

    Miyano, Hiroshi

    2008-01-01

    Background of preparation of standards, preparation of standards for development of nuclear power aging management technologies, revision of PLM (Product Lifecycle Management) standards, and problems of PLM standards are stated. The placement of social needs, scheme, the standards system, preparation of rules and standards, and practical use of them by road map are illustrated and explained. Relation between the safety regulations and examination standards, and development and preparation of standards system are outlined. The nuclear power plant aging management and the maintenance control are provided by many rules and standards. PLM standards defines the aging phenomena and extracts the measurements and reflects them on the usual maintenance flow under the long term maintenance program. New examination system constructs the usual maintenance and the maintenance based on the aging management and long term maintenance program. Outline and construction of PLM standards are explained with notes and additional books. (S.Y.)

  6. A Study on distinguishing seismic waves caused by natural earthquakes and underground nuclear explosion within North Korean Context

    Science.gov (United States)

    Premlet, B.; Sabu, S.; Kamarudheen, R.; Subair, S.

    2017-12-01

    Since the first nuclear test on 15 July 1945 , there have been over 2,051 other weapon tests around the world . The waveforms of a natural earthquake which generates strong S waves and an underground explosion which is dominated by P waves were distinguished from the analysis of data corresponding to a 2005 M5.0 Earthquake and a 2016 North Korean nuclear test , both at similar distances from seismometer . Further differences between the seismograms were evaluated and successfully distinguished between the origins of the elastic waves through the data using Moment Tensor Solution using stations BJT , HIA and INCN . North Korea has developed a nuclear fuel cycle capability and has both plutonium and enriched uranium programs at Pyongyang . Seismic recordings of vertical ground motion at Global Seismographic Network station IC.MDJ of the 4 seismic events at Punggye-ri , North Korea , which occurred on the 9th of October 2006 , 25th of May 2009, 12th of February 2013 and on the 6th of January and 9th of September , 2016 were examined and the P waves of these seismic waves , which show very similar wave form , were inspected and compared to the seismic data of the latest underground nuclear test on the 3rd of September 2017 at 03:30 UTC at the same site which is many times more powerful than the previous tests . The country , which is the only nation to have tested nuclear weapons in this millennium , has successfully prevented the release of radioactive isotopes and hampered data collection but further studies were done using acoustic data which was analysed from sonograms of the 4 North Korean tests at station MDJ. The latest explosion data from 3rd September was also compared to 42 presumed underground explosions which occurred in China , India , the U.S.S.R , Iran , Turkey and recorded at Arkansas Seismic Network.

  7. ASME nuclear codes and standards risk management strategic plan

    International Nuclear Information System (INIS)

    Balkey, Kenneth R.

    2003-01-01

    Over the past 15 years, several risk-informed initiatives have been completed or are under development within the ASME Nuclear Codes and Standards organization. In order to better manage the numerous initiatives in the future, the ASME Board on Nuclear Codes and Standards has recently developed and approved a Risk Management Strategic Plan. This paper presents the latest approved version of the plan beginning with a background of applications completed to date, including the recent issuance of the ASME Standard for Probabilistic Risk Assessment (PRA) for Nuclear Power Plant Applications. The paper discusses potential applications within ASME Nuclear Codes and Standards that may require expansion of the PRA Standard, such as for new generation reactors, or the development of new PRA Standards. A long-term vision for the potential development and evolution to a nuclear systems code that adopts a risk-informed approach across a facility life-cycle (design, construction, operation, maintenance, and closure) is summarized. Finally, near term and long term actions are defined across the ASME Nuclear Codes and Standards organizations related to risk management, and related U.S. regulatory activities are also summarized. (author)

  8. Nuclear Knowledge Capture and IEC Standards

    International Nuclear Information System (INIS)

    Sheldon, J.

    2016-01-01

    Full text: An International Standard is a document, established by consensus and approved by a recognized body that provides, for common and repeated use, rules, guidelines or characteristics for activities or their results, aimed at the achievement of the optimum degree of order in a given context. As such, it is a mechanism for sharing knowledge in a particular field. The consensus process used to approve the content of standards ensures that the content is essentially peer-reviewed. This presentation will explain how International Standards are developed and used and their importance in the dissemination of scientific and engineering information. It will also explain the role of the IEC in ensuring that the process for developing standards meets the core principles of the Code of Good Practice of the WTO TBT agreement: transparency, openness, impartiality and consensus, effectiveness and relevance, coherence, and addressing the concerns of developing countries. (author

  9. Development of standard testing methods for nuclear-waste forms

    International Nuclear Information System (INIS)

    Mendel, J.E.; Nelson, R.D.

    1981-11-01

    Standard test methods for waste package component development and design, safety analyses, and licensing are being developed for the Nuclear Waste Materials Handbook. This paper describes mainly the testing methods for obtaining waste form materials data

  10. Accurate relative location estimates for the North Korean nuclear tests using empirical slowness corrections

    Science.gov (United States)

    Gibbons, S. J.; Pabian, F.; Näsholm, S. P.; Kværna, T.; Mykkeltveit, S.

    2017-01-01

    Declared North Korean nuclear tests in 2006, 2009, 2013 and 2016 were observed seismically at regional and teleseismic distances. Waveform similarity allows the events to be located relatively with far greater accuracy than the absolute locations can be determined from seismic data alone. There is now significant redundancy in the data given the large number of regional and teleseismic stations that have recorded multiple events, and relative location estimates can be confirmed independently by performing calculations on many mutually exclusive sets of measurements. Using a 1-D global velocity model, the distances between the events estimated using teleseismic P phases are found to be approximately 25 per cent shorter than the distances between events estimated using regional Pn phases. The 2009, 2013 and 2016 events all take place within 1 km of each other and the discrepancy between the regional and teleseismic relative location estimates is no more than about 150 m. The discrepancy is much more significant when estimating the location of the more distant 2006 event relative to the later explosions with regional and teleseismic estimates varying by many hundreds of metres. The relative location of the 2006 event is challenging given the smaller number of observing stations, the lower signal-to-noise ratio and significant waveform dissimilarity at some regional stations. The 2006 event is however highly significant in constraining the absolute locations in the terrain at the Punggye-ri test-site in relation to observed surface infrastructure. For each seismic arrival used to estimate the relative locations, we define a slowness scaling factor which multiplies the gradient of seismic traveltime versus distance, evaluated at the source, relative to the applied 1-D velocity model. A procedure for estimating correction terms which reduce the double-difference time residual vector norms is presented together with a discussion of the associated uncertainty. The modified

  11. Toward analytic aids for standard setting in nuclear regulation

    International Nuclear Information System (INIS)

    Brown, R.V.; O'Connor, M.F.; Peterson, C.R.

    1979-05-01

    US NRC promulgates standards for nuclear reprocessing and other facilities to safeguard against the diversion of nuclear material. Two broad tasks have been directed toward establishing performance criteria for standard settings: general-purpose modeling, and analysis specific to a particular performance criterion option. This report emphasizes work on the second task. Purpose is to provide a framework for the evaluation of such options that organizes the necessary components in a way that provides for meaningful assessments with respect to required inputs

  12. Quantitative and radiological assessment of PYRO-SFR closed fuel cycle against direct disposal of spent nuclear fuel from Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Khan, Muhammad Minhaj; Lee, Suhong; Cheong, Jaehak; Whang, Jooho [Kyunghee University, Seoul (Korea, Republic of)

    2016-12-15

    Calculations have been made to estimate the generation of SNF including Plutonium (Pu) and minor actinides (MAs) from PWR and PHWR NPPs by using the IAEA code Nuclear Fuel Cycle Simulation System (NFCSS) for the period of 2016, 2030 as 12 more NPPs will be added by the year 2029. In order to find the optimize option for SNF management through sustainable use of nuclear energy system and reduce the associated radiological risk, 4 scenarios to burnout the Pu and MAs are analyzed. Estimation for the amount of SNF including major radionuclides has made for the year of 2016, 2030, 2089 and 2109 with an approximate amount of 148,19.65MT, 248,34.6 MT, 41572.23 MT and 61272.24 MT of SNF will be generated respectively. Radioactivity and radiotoxicity is calculated in order to access the radiological risk in terms of ingestion. Four Transmutation strategies is predicted to make Korean NPPs sustainable by incorporating KALIMER-600 (Burner) reactor in Korean nuclear fleet with an approximate transmutation rate of 99.77%, 96.57%, 95.34% and 97.58% for MA only (scenario-1), (MA & Pu) scenario-2, scenario-3 (MA only till the year 2125) and scenario-4 MA & Pu till the year 2148) respectively.

  13. Major NSSS design features of the Korean next generation reactor

    International Nuclear Information System (INIS)

    Kim, Insk; Kim, Dong-Su

    1999-01-01

    In order to meet national needs for increasing electric power generation in the Republic of Korea in the 2000s, the Korean nuclear development group (KNDG) is developing a standardized evolutionary advanced light water reactor (ALWR), the Korean Next Generation Reactor (KNGR). It is an advanced version of the successful Korean Standard Nuclear Power Plant (KSNP) design, which meets utility needs for safety enhancement, performance improvement and ease of operation and maintenance. The KNGR design starts fro the proven design concept of the currently operating KSNPs with uprated power and advanced design features required by the utility. The KNGR design is currently in the final stage of the basic design, and the paper describes the major nuclear steam supply system (NSSS) design features of the KNGR together with introduction of the KNGR development program. (author)

  14. Future direction of ASME nuclear codes and standards

    International Nuclear Information System (INIS)

    Ennis, Kevin; Sheehan, Mark E.

    2003-01-01

    While the nuclear power industry in the US is in a period of stasis, there continues to be a great deal of activity in the ASME nuclear standards development arena. As plants age, the need for new approaches in standardization changes with the changing needs of the industry. New tools are becoming available in the form of risk analysis, and this is finding its way into more and more of ASME's standards activities. This paper will take a look at the direction that ASME nuclear Codes and Standards are heading in this and other areas, as well as taking a look at some advance reactor concepts and plans for standards to address new technologies

  15. U.S. and South Korean Cooperation in the World Nuclear Energy Market: Major Policy Considerations

    Science.gov (United States)

    2010-01-21

    system and other major components. • Samsung C&T Corporation. Plant construction. • Hyundai Engineering and Construction. Plant construction...market. Other countries that have been mentioned in the news media include Vietnam, Malaysia , Thailand, and Middle East neighbors of the UAE.25 A Korean

  16. Standard leach tests for nuclear waste materials

    International Nuclear Information System (INIS)

    Strachan, D.M.; Barnes, B.O.; Turcotte, R.P.

    1980-01-01

    Five leach tests were conducted to study time-dependent leaching of waste forms (glass). The first four tests include temperature as a variable and the use of three standard leachants. Three of the tests are static and two are dynamic (flow). This paper discusses the waste-form leach tests and presents some representative data. 4 figures

  17. Status of ANSI standards on decommissioning of nuclear reprocessing facilities

    International Nuclear Information System (INIS)

    Graham, H.B.

    1975-01-01

    A definition of decommissioning is given, and the preparation of ANSI Standard, ''General Design Criteria for Nuclear Reprocessing Facilities'' (N101.3) is discussed. A Eurochemic report, entitled ''The Shutdown of Reprocessing Facilities--Results of Preliminary Studies on the Installations Belonging to Eurochemic,'' was used in the preparation of this standard. (U.S.)

  18. The IAEA safety standards for radiation, waste and nuclear safety

    International Nuclear Information System (INIS)

    Gonzalez, Abel J.

    1997-01-01

    This paper presents a brief description of the standards for radiation, waste and nuclear safety established by the International Atomic Energy Agency (IAEA). It provides a historical overview of their development and also summarizes the standards' current preparation and review process. The final paragraphs offer an outlook on future developments. (author)

  19. Present problems of standardization in nuclear instrumentation in Romania

    International Nuclear Information System (INIS)

    Purghel, Lidia

    2001-01-01

    The continuos development of nuclear techniques, based on international cooperation, led to the need for producing national and international standards referring to terminology, classification, technical characteristic, testing and calibration methods for nuclear instrumentation. The international standardization activity is organised in the frame of the well-known organization like IEC, ISO, ICRU, ICRP, IOLM, CENELEC, EFOMP, WHO. High advances were obtained in the standardization of the ionising radiation dosimetry in the frame of the International Commission for Radiation Units (ICRU) which started its works 1925. Romania is member of the International Electrotechnical Commission (IEC) from 1920 when its president was the formal member of Romanian Academy, professor Remus Radulet. Romania is effectively involved in standardization activities in the field nuclear instrumentation both as user and manufacturer of nuclear instrumentation. At national level the Technical Committee 45, as a branch of the Romanian Electrotechnical Committee is hosted by Horia Hulubei National Institute for Physics and Nuclear Engineering. The technical committee has the tasks of analysing the market, the regulations and the industry requirements and proposing new standards or revision for existing one. A table is given showing the number of IEC standards considered by TC 45, adopted RS - IEC standards (prepared/published) and planned for 2000/2001. Romania hosted IEC international plenary meetings in 1962 and 1974 and an IEC workshop 1997 with participation of specialists from USA, Sweden, Germany, France, Japan and Romania. As industry is striving to use more and more standard products, that means best quality and safety for less money, more than ever one have to convince the industry about the usefulness and specificity of the nuclear standards

  20. Radiological and nuclear safety- evolution, standards and similarity

    International Nuclear Information System (INIS)

    Soman, S.D.

    1996-01-01

    With the realisation of potential for severe health affects after the discovery of x-rays and radioactivity, the radiation protection aspect became focus of interest for medical users from the beginning of this century. With the activities of International Commission on Radiological Protection (ICRP), the standards evolved during all these years based on epidemiological data and radio-biological research. The current standards are the ICRP recommendations of 1990. Based on these, internationally harmonised standards for protection against ionising radiation and safety of radioactive sources were brought out by IAEA in 1994. The nuclear safety (implies safety of nuclear power plants) came into prominence when large scale units were designed and operated since mid 1950s. The philosophy in nuclear safety has evolved in past 2-3 decades taking into account the lessons learned from accidents, mainly Three Mile Island (1979) and Chernobyl-4 (1986). These current nuclear safety standards are incorporated in INSAG reports, particularly INSAG-3. This paper brings out salient features of these evolutions, current standards and similarity of radiation and nuclear safety standards in their present form. (author). 7 refs., 10 tabs

  1. Trends in U.S. nuclear standards development

    International Nuclear Information System (INIS)

    Crowley, J.H.; Kaminski, R.S.

    1987-01-01

    Regulation of the U.S Nuclear Power industry has been extensive during the 1970's. Key to this situation has been the evolution in the 'interpretation' of the rules, regulations and consensus standards which have been incorporated into NRC guidance documents by reference or endorsement. The resulting increase in the number and complexity of LWR construction requirements has significantly increased the labor content of an LWR construction project. The authors believe that existing nuclear related consensus standards should be reviewed with the objective of modifying the standards to improve the efficiency and productivity of engineering, craft, and non-manual personnel. (author)

  2. ASME nuclear codes and standards risk management strategic planning

    International Nuclear Information System (INIS)

    Hill, Ralph S. III; Balkey, Kenneth R.; Erler, Bryan A.; Wesley Rowley, C.

    2007-01-01

    This paper is prepared in honor and in memory of the late Professor Emeritus Yasuhide Asada to recognize his contributions to ASME Nuclear Codes and Standards initiatives, particularly those related to risk-informed technology and System Based Code developments. For nearly two decades, numerous risk-informed initiatives have been completed or are under development within the ASME Nuclear Codes and Standards organization. In order to properly manage the numerous initiatives currently underway or planned for the future, the ASME Board on Nuclear Codes and Standards (BNCS) has an established Risk Management Strategic Plan (Plan) that is maintained and updated by the ASME BNCS Risk Management Task Group. This paper presents the latest approved version of the plan beginning with a background of applications completed to date, including the recent probabilistic risk assessment (PRA) standards developments for nuclear power plant applications. The paper discusses planned applications within ASME Nuclear Codes and Standards that will require expansion of the ASME PRA Standard to support new advanced light water reactor and next generation reactor developments, such as for high temperature gas-cooled reactors. Emerging regulatory developments related to risk-informed, performance- based approaches are summarized. A long-term vision for the potential development and evolution to a nuclear systems code that adopts a risk-informed approach across a facility life-cycle (design, construction, operation, maintenance, and closure) is also summarized. Finally, near term and long term actions are defined across the ASME Nuclear Codes and Standards organizations related to risk management, including related U.S. regulatory activities. (author)

  3. A study on the impact of the new international rules of the game (UR, the agreement on government procurement) and on the countermeasures for the Korean nuclear industry

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kwang Suk; Song, Kee Dong; Ham, Chul Hoon; Kim, Seung Soo; Koh, Han Suk [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1994-08-01

    The purpose of this study is to analyze the impact of such changes in the rules of the game on the Korean nuclear industry and to propose possible countermeasures in short-term and long-term perspectives at the national level. This study also has an educational purpose to help people. working in the nuclear field understand the significance of the changes in the rules of the game. This study looks through the history and contents of the GATT system, the UR, the AGP, and the post-UR movement, providing some insight on the current trend in the rules of the game. Also this study analyzes the impact of the changes in the rules of the game on the Korean nuclear industry in qualitative terms, and proposes possible short-term and long-term countermeasures at the national level in both perspectives of utility and nuclear industry. 5 figs, 15 tabs, 51 refs. (Author).

  4. A study on the impact of the new international rules of the game (UR, the agreement on government procurement) and on the countermeasures for the Korean nuclear industry

    International Nuclear Information System (INIS)

    Lee, Kwang Suk; Song, Kee Dong; Ham, Chul Hoon; Kim, Seung Soo; Koh, Han Suk

    1994-08-01

    The purpose of this study is to analyze the impact of such changes in the rules of the game on the Korean nuclear industry and to propose possible countermeasures in short-term and long-term perspectives at the national level. This study also has an educational purpose to help people. working in the nuclear field understand the significance of the changes in the rules of the game. This study looks through the history and contents of the GATT system, the UR, the AGP, and the post-UR movement, providing some insight on the current trend in the rules of the game. Also this study analyzes the impact of the changes in the rules of the game on the Korean nuclear industry in qualitative terms, and proposes possible short-term and long-term countermeasures at the national level in both perspectives of utility and nuclear industry. 5 figs, 15 tabs, 51 refs. (Author)

  5. The nuclear problem in Northeast Asia and ways to resolve it: A North Korean perspective

    International Nuclear Information System (INIS)

    Pae Sang Hak

    1995-01-01

    The end of the Cold War worldwide has added new momentum to the process of nuclear disarmament. However, vestiges of the Cold War have yet to be removed from Northeast Asia, where the nuclear threat has snowballed. This chapter examines potential nuclear dangers in Northeast Asia - a region which has the greatest concentration of nuclear weapons bases and nuclear weapons in the world

  6. American National Standard: nuclear data sets for reactor design calculations

    International Nuclear Information System (INIS)

    1983-01-01

    This standard identifies and describes the specifications for developing, preparing, and documenting nuclear data sets to be used in reactor design calculations. The specifications include criteria for acceptance of evaluated nuclear data sets, criteria for processing evaluated data and preparation of processed continuous data and averaged data sets, and identification of specific evaluated, processed continuous, and averaged data sets which meet these criteria for specific reactor types

  7. American National Standard nuclear data sets for reactor design calculations

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    A standard is presented which identifies and describes the specifications for developing, preparing, and documenting nuclear data sets to be used in reactor design calculations. The specifications include (a) criteria for acceptance of evaluated nuclear data sets, (b) criteria for processing evaluated data and preparation of processed continuous data and averaged data sets, and (c) identification of specific evaluated, processed continuous, and averaged data sets which meet these criteria for specific reactor types

  8. Developing a Korean standard brain atlas on the basis of statistical and probabilistic approach and visualization tool for functional image analysis

    Energy Technology Data Exchange (ETDEWEB)

    Koo, B. B.; Lee, J. M.; Kim, J. S.; Kim, I. Y.; Kim, S. I. [Hanyang University, Seoul (Korea, Republic of); Lee, J. S.; Lee, D. S.; Kwon, J. S. [Seoul National University College of Medicine, Seoul (Korea, Republic of); Kim, J. J. [Yonsei University College of Medicine, Seoul (Korea, Republic of)

    2003-06-01

    The probabilistic anatomical maps are used to localize the functional neuro-images and morphological variability. The quantitative indicator is very important to inquire the anatomical position of an activated region because functional image data has the low-resolution nature and no inherent anatomical information. Although previously developed MNI probabilistic anatomical map was enough to localize the data, it was not suitable for the Korean brains because of the morphological difference between Occidental and Oriental. In this study, we develop a probabilistic anatomical map for Korean normal brain. Normal 75 brains of T1-weighted spoiled gradient echo magnetic resonance images were acquired on a 1.5-T GESIGNA scanner. Then, a standard brain is selected in the group through a clinician searches a brain of the average property in the Talairach coordinate system. With the standard brain, an anatomist delineates 89 regions of interest (ROI) parcellating cortical and subcortical areas. The parcellated ROIs of the standard are warped and overlapped into each brain by maximizing intensity similarity. And every brain is automatically labeled with the registered ROIs. Each of the same-labeled region is linearly normalize to the standard brain, and the occurrence of each region is counted. Finally, 89 probabilistic ROI volumes are generated. This paper presents a probabilistic anatomical map for localizing the functional and structural analysis of Korean normal brain. In the future, we'll develop the group specific probabilistic anatomical maps of OCD and schizophrenia disease.

  9. Developing a Korean standard brain atlas on the basis of statistical and probabilistic approach and visualization tool for functional image analysis

    International Nuclear Information System (INIS)

    Koo, B. B.; Lee, J. M.; Kim, J. S.; Kim, I. Y.; Kim, S. I.; Lee, J. S.; Lee, D. S.; Kwon, J. S.; Kim, J. J.

    2003-01-01

    The probabilistic anatomical maps are used to localize the functional neuro-images and morphological variability. The quantitative indicator is very important to inquire the anatomical position of an activated region because functional image data has the low-resolution nature and no inherent anatomical information. Although previously developed MNI probabilistic anatomical map was enough to localize the data, it was not suitable for the Korean brains because of the morphological difference between Occidental and Oriental. In this study, we develop a probabilistic anatomical map for Korean normal brain. Normal 75 brains of T1-weighted spoiled gradient echo magnetic resonance images were acquired on a 1.5-T GESIGNA scanner. Then, a standard brain is selected in the group through a clinician searches a brain of the average property in the Talairach coordinate system. With the standard brain, an anatomist delineates 89 regions of interest (ROI) parcellating cortical and subcortical areas. The parcellated ROIs of the standard are warped and overlapped into each brain by maximizing intensity similarity. And every brain is automatically labeled with the registered ROIs. Each of the same-labeled region is linearly normalize to the standard brain, and the occurrence of each region is counted. Finally, 89 probabilistic ROI volumes are generated. This paper presents a probabilistic anatomical map for localizing the functional and structural analysis of Korean normal brain. In the future, we'll develop the group specific probabilistic anatomical maps of OCD and schizophrenia disease

  10. Thirty years of international nuclear standards in ISO and IEC

    International Nuclear Information System (INIS)

    Becker, K.

    1991-01-01

    Of over 4700 nuclear and radiation protection standards, laws, regulations, recommendations, etc., which have been issued by 52 countries and several governmental international organizations such as IAEA, or non-government organizations such as ICRP, ICRU, ISO and IEC, more than 90% are national, and more than half of those of a non-regulatory nature. Both number and importance of international standards are, however, increasing. The two most important non-governmental international standards organizations are the International Organization for Standardization (ISO), which founded a Technical Committee (TC) 85 'Nuclear Energy' with several Sub-Committees in 1957, and the closely associated International Electrotechnical Commission (IEC) with its TC 45 'Nuclear Instrumentation' formed in 1960. There are over 20 member countries actively participating in the work in each of them, with additional observer countries and liaison to the relevant other international organizations. A brief review is given on some of the experience which has been gained by ISO/TC 85 and IEC/TC 45, and its work program and accomplishments, considering in particular recent developments. It covers nuclear safety and instrumentation, radiation protection, and the nuclear fuel cycle, as well as interface issues including definitions and terminology, interaction of the activities with the work of other national and international bodies, etc. Some problem areas are also briefly discussed. (orig.)

  11. Principles and standards of nuclear safety and their implementation

    International Nuclear Information System (INIS)

    Franzen, L.F.

    1979-01-01

    Nuclear safety starts with the design of a nuclear facility and is only completed with its decommissioning. In the various phases of a nuclear facility's lifetime, safety evaluations are required. The licensing prerequisites for construction, operation, modification, decommissioning are based on elements of the relevant national legislation and related ordinances as well as on international regulations. They should be expanded by a system of criteria and standards spelling out the proven practice as developed over the last decades in the industrialized countries and by international organizations such IAEA with its safety codes and guides. (NEA) [fr

  12. Standards for psychological assessment of nuclear facility personnel. Technical report

    International Nuclear Information System (INIS)

    Frank, F.D.; Lindley, B.S.; Cohen, R.A.

    1981-07-01

    The subject of this study was the development of standards for the assessment of emotional instability in applicants for nuclear facility positions. The investigation covered all positions associated with a nuclear facility. Conclusions reached in this investigation focused on the ingredients of an integrated selection system including the use of personality tests, situational simulations, and the clinical interview; the need for professional standards to ensure quality control; the need for a uniform selection system as organizations vary considerably in terms of instruments presently used; and the need for an on-the-job behavioral observation program

  13. standards used for quality control of nuclear fuels

    International Nuclear Information System (INIS)

    Guereli, L; Can, S.

    1997-01-01

    Nuclear fuels and fuel materials are subject to stringent restrictions as to their quality. The standards and regulations that apply vary according to reactor type and country and the standards are stated in the quality assurance documents. The concept of quality assurance has altered the conventional quality control tests and procedures, defining which control tests are to be applied and how. Although most of the tests and measurements allow the determination of tolerances to be decided according to the agreement between the buyer and the seller, exacting procedures apply to which instruments and equipment are used for these tests and measurements, how these instruments are standardized.Detailed explanations of test methods and their documentation is a requirement in all standards. The purpose of this work is to study which standards, tests and measurements apply to the nuclear fuel production. Only the standards that apply to various stages of the nuclear fuel production (powder preparation, pellet production, fuel element and fuel assembly fabrication) are reviewed. Process and documentation control, design and licensing requirements and the frequency of inspections are quality assurance subjects. Some ASTM standards are given as examples

  14. Things Korean.

    Science.gov (United States)

    Chang, Roberta

    Presented in this booklet are brief descriptions of items and activities that are symbolic of Korean culture. Some of the items and activities described include traditional Korean clothing and accessories, dolls, fans, a Korean game called "yut," tape recordings of Korean music, a "buhk" (drum), and brass eating utensils. A map of Korea, some…

  15. Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

  16. Standard specification for nuclear-grade zirconium oxide powder

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    1.1 This specification defines the physical and chemical requirements for zirconium oxide powder intended for fabrication into shapes, either entirely or partially of zirconia, for use in a nuclear reactor core. 1.2 The material described herein shall be particulate in nature. 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

  17. Technology standards for structure, etc. concerning nuclear power generating facilities

    International Nuclear Information System (INIS)

    1977-01-01

    Based on the Ordinance for the Technology Standards concerning Nuclear Power Generating Facilities, the technology standards are established for the vessels of class 1 to 4 (including reactor pressure vessels, reactor containment vessels, etc.), the pipes of class 1 to 3, safety valves, pressure test and monitoring test specimens. Those specified are materials, nondestructive tests, structures, shapes, shells, flanges, etc. for the vessels and the pipes, and so on. (Mori, K.)

  18. Nuclear safety: operational aspects. 5. Data Communication in a Nuclear Digital I and C System-The Korean Experience

    International Nuclear Information System (INIS)

    Lim, Tae-Wook; Byun, Jae-Youb; Jhun, James S.

    2001-01-01

    Full-scale use of a microprocessor-based digital instrumentation and control (I and C) system for the control of nuclear power plants (NPPs) in Korea has spanned >14 yr and has covered eight plants. Experience gained from these applications is substantial. In this paper, the discussion centers on the design experience of the data communication portion of the digital I and C system along with the associated nuclear licensing issues. The data communication designs of the eight plants (four operating and four under construction) have changed from project to project and from supplier to supplier. The first two of the eight plants, Yonggwang NPP (YGN) Units 3 and 4 (YGN-3 and 4) included only the on/off (binary) controls in the digital I and C system. The subsequent six plants had a fully expanded scope of plant controls including both on/off controls as well as continuous (analog) controls. These latter six plants are Ulchin NPP (UCN) Units 3 and 4 (UCN 3 and 4), YGN Units 5 and 6 (YGN 5 and 6), and UCN Units 5 and 6 (UCN 5 and 6) in the order of their construction start dates. The digital system suppliers are Forney for YGN 3 and 4 and UCN 5 and 6; and Eaton for UCN 3 and 4 and YGN 5 and 6. The Forney system uses bus network architecture, while the Eaton system is based on a ring network configuration. The design differences, advantages, disadvantages, and specific licensing issues of these two configurations unique to the NPP operating environment are discussed in the abstract. The discussions are organized into two parts: the Forney system of YGN 3 and 4 and the Eaton system of YGN 5 and 6. The Forney system of UCN 5 and 6 is still in its early stage of design and manufacture, and it is basically similar to the design of YGN 3 and 4 except for the system upgrade from a 16- to a 32-bit system and the addition of an analog plant monitoring and control function. The Eaton system of UCN 3 and 4 is essentially identical to that of YGN 5 and 6 except that the YGN 5 and 6

  19. Personnel involved in nuclear standards development: 1980 directory

    International Nuclear Information System (INIS)

    Carr, S.J.

    1980-03-01

    The development of nuclear standards is an active and necessary endeavor that is concerned with the safe, orderly, and economic development of nuclear potential. There are almost 4100 people from the teachnical community who are presently involved either in writing nuclear standards, including codes, or in the management and processing roles necessary for their approval and promulgation. This document identifies the current participation of each individual as member, chairman, cochairman (vice-chairman), or secretary of about 700 standards development committees and groups. The standards committees and groups are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. This directory includes four major sections: personnel, employers, committees, and a Key-Word-in-Context (KWIC) Index of committee titles. It can also be used to identify the participation of employers as well as to recognize the contributions of individuals to the often interdisciplinary activity of standards development

  20. Personnel involved in nuclear standards development: 1980 directory

    Energy Technology Data Exchange (ETDEWEB)

    Carr, S.J. (ed.)

    1980-03-01

    The development of nuclear standards is an active and necessary endeavor that is concerned with the safe, orderly, and economic development of nuclear potential. There are almost 4100 people from the teachnical community who are presently involved either in writing nuclear standards, including codes, or in the management and processing roles necessary for their approval and promulgation. This document identifies the current participation of each individual as member, chairman, cochairman (vice-chairman), or secretary of about 700 standards development committees and groups. The standards committees and groups are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. This directory includes four major sections: personnel, employers, committees, and a Key-Word-in-Context (KWIC) Index of committee titles. It can also be used to identify the participation of employers as well as to recognize the contributions of individuals to the often interdisciplinary activity of standards development.

  1. Renovated Korean nuclear safety and security system: A review and suggestions to successful settlement

    Energy Technology Data Exchange (ETDEWEB)

    Chung, W. S.; Yun, S. W.; Lee, D. S. [Korea Atomic Energy Research Inst., Dukjin-dong 150, Yusung-gu, Daejon, R.O., 305-353 (Korea, Republic of); Go, D. Y. [Kyung Hee Univ., Kyung Hee daero 26, Dongdaemoon-gu, Seoul, R.O., 130-701 (Korea, Republic of)

    2012-07-01

    Questions of whether past nuclear regulatory body of Korea is not a proper system to monitor and check the country's nuclear energy policy and utilization have been raised. Moreover, a feeling of insecurity regarding nuclear safety after the nuclear accident in Japan has spread across the public. This has stimulated a renovation of the nuclear safety regime in Korea. The Nuclear Safety and Security Commission (NSSC) was launched on October 26, 2011 as a regulatory body directly under the President in charge of strengthening independence and nuclear safety. This was a meaningful event as the NSSC it is a much more independent regulatory system for Korea. However, the NSSC itself does not guarantee an enhanced public acceptance of the nuclear policy and stable use nuclear energy. This study introduces the new NSSC system and its details in terms of organization structure, appropriateness of specialty, budget stability, and management system. (authors)

  2. Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Ji Hyun; Lee, Bong Sang [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2017-08-15

    The precise prediction of radiation embrittlement of aged reactor pressure vessels (RPVs) is a prerequisite for the long-term operation of nuclear power plants beyond their original design life. The expiration of the operation licenses for Korean reactors the RPVs of which are made from SA533B-1 plates and welds is imminent. Korean regulatory rules have adopted the US Nuclear Regulatory Commission's transition temperature shift (TTS) models to the prediction of the embrittlement of Korean reactor pressure vessels. The applicability of the TTS model to predict the embrittlement of Korean RPVs made of SA533B-1 plates and welds was investigated in this study. It was concluded that the TTS model of 10 CFR 50.61a matched the trends of the radiation embrittlement in the SA533B-1 plates and welds better than did that of Regulatory Guide (RG) 1.99 Rev. 2. This is attributed to the fact that the prediction performance of 10 CFR 50.61a was enhanced by considering the difference in radiation embrittlement sensitivity among the different types of RPV materials.

  3. Merits and difficulties in adopting codes, standards and nuclear regulations

    International Nuclear Information System (INIS)

    El-Saiedi, A.F.; Morsy, S.; Mariy, A.

    1978-01-01

    Developing countries planning for introducing nuclear power plants as a source of energy have to develop or adopt sound regulatory practices. These are necessary to help governmental authorities to assess the safety of nuclear power plants and to perform inspections needed to confirm the established safe and sound limits. The first requirement is to form an independent regulatory body capable of setting up and enforcing proper safety regulations. The formation of this body is governed by several considerations related to local conditions in the developing countries, which may not always be favourable. It is quite impractical for countries with limited experience in the nuclear power field to develop their own codes, standards and regulations required for the nuclear regulatory body to perform its tasks. A practical way is to adopt codes, standards and regulations of a well-developed country. This has merits as well as drawbacks. The latter are related to problems of personnel, software, equipment and facilities. The difficulties involved in forming a nuclear regulatory body, and the merits and difficulties in adopting foreign codes, standards and regulations required for such body to perform its tasks, are discussed in this paper. Discussions are applicable to many developing countries and particular emphasis is given to the conditions and practices in Egypt. (author)

  4. A nuclear standard high-efficiency adsorber for iodine

    International Nuclear Information System (INIS)

    Wang Jianmin; Qian Yinge

    1988-08-01

    The structure of a nuclear standard high-efficiency adsorber, adsorbent and its performance are introduced. The performance and structure were compared with the same kind product of other firms. The results show that the leakage rate is less than 0.005%

  5. Standard Specification for Nuclear Grade Zirconium Oxide Pellets

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This specification applies to pellets of stabilized zirconium oxide used in nuclear reactors. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

  6. INDC/NEANDC nuclear standards file 1980 version

    International Nuclear Information System (INIS)

    1981-09-01

    This working document of the Nuclear Standards Subcommittee of the International Nuclear Data Committee (INDC) summarizes the status of nuclear standards as of the 11th INDC meeting (6/'80) with selective updating to approximately 5/'81. This version of the file is presented in two sections as per the following. The first section (A) consists of numerical tabulations of the respective quantities generally including quantitative definition of the uncertainties. Most of these numerical values are taken from the ENDF/B-V file which is available on a world-wide basis through the 4-Center network. Some guidelines as to appropriate usage are also given. The objective is the provision of a concise and readily used reference guide to essential standard-nuclear quantities useful for a diversity of basic and applied endeavors. The second section (B) briefly summarizes the contemporary status of each of the standards tabulated in Section A and additional items, including recent relevant work and areas of continuing uncertainty. These brief reviews were prepared under the auspices of the Committee by outstanding specialists in the respective fields. In many instances they are new statements but, where review indicates that the previous statement (see INDC-30/L+sp) remains appropriate, the previous summaries were retained; often with additional remarks by the editor

  7. International standardization of nuclear reactor designs - the way forward

    International Nuclear Information System (INIS)

    Raetzke, Christian

    2010-01-01

    The concept of 'International Standardization of Nuclear Reactor Designs' means that vendors could build their designs in every country without having to adapt it specifically to national safety requirements. Such standardization would have two main effects. It would greatly facilitate nuclear new build worldwide by giving greater efficiency and certainty to the national licensing procedures; by taking into account the fact that vendors, and nowadays also utilities, are active across borders; by helping developing countries to establish their nuclear new build programmes; and by reducing the strain on human resources on both the regulators' and the industry's side. The second valuable effect of standardization would be to further enhance safety by improving the exchange of construction and operating experience among a number of reactors belonging to fleets of the same design. The World Nuclear Association's CORDEL (Cooperation in Reactor Design Evaluation and Licensing) Group has developed a concept for implementation of international standardization of reactor designs. It has defined a number of steps to be taken by industry. At the same time, possibilities offered by national and international regulatory mechanisms would have to be fully made use of, and some changes in regulatory frameworks might be necessary. Some steps especially towards greater cooperation of regulators have already been taken; however, much still remains to be done. The concept of deploying standardized reactor designs across a number of countries supposes an alignment and, if possible, harmonization of national safety standards; a streamlining of national licensing procedures, making them more efficient and predictable; and the willingness of national regulators to take into account licensing done in other countries. In the end, this should lead to a mutual acceptance of design approvals or, in a more distant future, even to a multinational design approval process. All in all, the concept

  8. Internationally Standardized Cost Item Definitions for Decommissioning of Nuclear Installations

    International Nuclear Information System (INIS)

    Lucien Teunckens; Kurt Pflugrad; Candace Chan-Sands; Ted Lazo

    2000-01-01

    The European Commission (EC), the International Atomic Energy Agency (IAEA), and the Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA) have agreed to jointly prepare and publish a standardized list of cost items and related definitions for decommissioning projects. Such a standardized list would facilitate communication, promote uniformity, and avoid inconsistency or contradiction of results or conclusions of cost evaluations for decommissioning projects carried out for specific purposes by different groups. Additionally, a standardized structure would also be a useful tool for more effective cost management. This paper describes actual work and result thus far

  9. Korean soft weather

    International Nuclear Information System (INIS)

    Pressburg, A.P.

    2007-01-01

    In this paper author deals with the development of nuclear weapons in the Korean People Democratic Republic (North Korea), which was crowned in October 2006 with the first successful underground detonation of nuclear charge. The North Korea so walked into the elite club and became de facto the nuclear great power. Nuclear disarmament negotiations with North Korea misfired. Relationships between the North Korea and the Republic of Korea as well as the China are discussed

  10. ASME nuclear codes and standards: Recent technical initiatives

    International Nuclear Information System (INIS)

    Feigel, R. E.

    1995-01-01

    Although nuclear power construction is currently in a hiatus in the US, ASME and its volunteer committees remain committed to continual improvements in the technical requirements in its nuclear codes. This paper provides an overview of several significant recent revisions to ASME' s nuclear codes. Additionally, other important initiatives currently being addressed by ASME committees will be described. With the largest population of operating light water nuclear plants in the world and worldwide use of its nuclear codes, ASME continues to support technical advancements in its nuclear codes and standards. While revisions of various magnitude are an ongoing process, several recent revisions embody significant changes based on state of the art design philosophy and substantial industry experience. In the design area, a significant revisions has recently been approved which will significantly reduce conservatisms in seismic piping design as well as provide simplified design rules. Major revisions have also been made to the requirements for nuclear material manufacturers and suppliers, which should result in clearer understanding of this difficult administrative area of the code. In the area of Section XI inservice rules, substantial studies are underway to investigate the application of probabilistic, risked based inspection in lieu of the current deterministic inspection philosophy. While much work still is required in this area, it is an important potential application of the emerging field of risk based inspection

  11. International implications of nuclear Q.A. standards

    International Nuclear Information System (INIS)

    Stoddart, D.E.

    1976-01-01

    The work of the International Atomic Energy Agency (I.A.E.A.) in the field of Quality Assurance is aimed at preparing a Code of Practice covering recommendations on safety aspects only which is designed to be usable by all nations. This Code is followed up by a series of Safety Guides as aids to developing nations faced with the need to regulate and assure safety, reliability and quality. The I.A.E.A. Code is not written as a mandatory document and it can only recommend and therefore the term 'should' is used throughout. The International Organization for Standardization (I.S.O.) is concerned with producing standards and as such the proposed I.S.O. draft standard on 'Quality Assurance for Nuclear Power Plants' is written in mandatory language, it uses the word 'shall'. The I.S.O. standard will also cover not only safety aspects but also those of a successfully operating nuclear power plant. The I.S.O. Working Group is charged with producing standards on quality assurance covering the design, procurement, fabrication, construction, operation, maintenance and decommissioning of structure, systems and components of nuclear power plants. The work of both organizations is discussed briefly. (author)

  12. Survey of Regulations Applicable to the Finned Containment in Korean Nuclear Power Plant for Light Water Reactor

    International Nuclear Information System (INIS)

    Noh, Hyung Gyun; Kang, Hie Chan

    2016-01-01

    In severe accident, the molten corium would discharge into the reactor cavity and interact with water and concrete of cavity. Molten corium includes non-oxidation metals such as Zr, Fe and Cr. These metal species reacted with water emit hydrogen gas. In addition to this, a mount of steam can be emitted to the containment such as steam line break accident. As a result, steam and hydrogen gas can pressurize containment over the design pressure and threaten its integrity. For this reasons, a concept equipped with finned on the containment building was proposed for coping with prolonged accident. Finned containment can enhance heat transfer to the ambient, and the building itself is working as a heat sink. Multiple metal fins and metal rod are penetrated into containment wall, and the rods are working as an additional path of heat removal. To be accepted in the nuclear power plants, this configuration should satisfy the requirement of heat removal and follow all regulations related with containment also. For applying to Korean nuclear power plants, the finned containment should follow all regulations specialized in Korea such as Nuclear regulatory criteria for light water reactor and Guidelines of nuclear safety examination for light water reactor. A concept of containment as a passive cooling system has been proposed. Furthermore, the new containment concept can be applied on the real containment which satisfies the various regulations. Finned containment would be expected positive effects on heat removal from the containment. If the fins are properly welded to the liner, finned containment could satisfy the leak tightness and prevention of external influences. Finned containment could be favorable to protect external impact like aircraft crash because of the additional structural integrity by the fins

  13. Survey of Regulations Applicable to the Finned Containment in Korean Nuclear Power Plant for Light Water Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Noh, Hyung Gyun [Pohang University, Pohang (Korea, Republic of); Kang, Hie Chan [Kunsan University, Gunsan (Korea, Republic of)

    2016-05-15

    In severe accident, the molten corium would discharge into the reactor cavity and interact with water and concrete of cavity. Molten corium includes non-oxidation metals such as Zr, Fe and Cr. These metal species reacted with water emit hydrogen gas. In addition to this, a mount of steam can be emitted to the containment such as steam line break accident. As a result, steam and hydrogen gas can pressurize containment over the design pressure and threaten its integrity. For this reasons, a concept equipped with finned on the containment building was proposed for coping with prolonged accident. Finned containment can enhance heat transfer to the ambient, and the building itself is working as a heat sink. Multiple metal fins and metal rod are penetrated into containment wall, and the rods are working as an additional path of heat removal. To be accepted in the nuclear power plants, this configuration should satisfy the requirement of heat removal and follow all regulations related with containment also. For applying to Korean nuclear power plants, the finned containment should follow all regulations specialized in Korea such as Nuclear regulatory criteria for light water reactor and Guidelines of nuclear safety examination for light water reactor. A concept of containment as a passive cooling system has been proposed. Furthermore, the new containment concept can be applied on the real containment which satisfies the various regulations. Finned containment would be expected positive effects on heat removal from the containment. If the fins are properly welded to the liner, finned containment could satisfy the leak tightness and prevention of external influences. Finned containment could be favorable to protect external impact like aircraft crash because of the additional structural integrity by the fins.

  14. Nuclear anapole moment and tests of the standard model

    International Nuclear Information System (INIS)

    Flambaum, V. V.

    1999-01-01

    There are two sources of parity nonconservation (PNC) in atoms: the electron-nucleus weak interaction and the magnetic interaction of electrons with the nuclear anapole moment. A nuclear anapole moment has recently been observed. This is the first discovery of an electromagnetic moment violating fundamental symmetries--the anapole moment violates parity and charge-conjugation invariance. We describe the anapole moment and how it can be produced. The anapole moment creates a circular magnetic field inside the nucleus. The interesting point is that measurements of the anapole allow one to study parity violation inside the nucleus through atomic experiments. We use the experimental result for the nuclear anapole moment of 133 Cs to find the strengths of the parity violating proton-nucleus and meson-nucleon forces. Measurements of the weak charge characterizing the strength of the electron-nucleon weak interaction provide tests of the Standard Model and a way of searching for new physics beyond the Standard Model. Atomic experiments give limits on the extra Z-boson, leptoquarks, composite fermions, and radiative corrections produced by particles that are predicted by new theories. The weak charge and nuclear anapole moment can be measured in the same experiment. The weak charge gives the mean value of the PNC effect while the anapole gives the difference of the PNC effects for the different hyperfine components of an electromagnetic transition. The interaction between atomic electrons and the nuclear anapole moment may be called the ''PNC hyperfine interaction.''

  15. Regulatory practices and safety standards for nuclear power plants

    International Nuclear Information System (INIS)

    1989-01-01

    The International Symposium on Regulatory Practices and Safety Standards for Nuclear Power Plants was jointly organized by the International Atomic Energy Agency (IAEA), for Nuclear Energy Agency of the OECD and the Government of the Federal Republic of Germany with the objective of providing an international forum for the exchange of information on regulatory practices and safety standards for nuclear power plants. The Symposium was held in Munich, Federal Republic of Germany, from 7 to 10 November 1988. It was attended by 201 experts from some 32 Member States and 4 international organizations. Fifty-one papers from 19 Member States and 2 international organizations were presented and discussed in 5 technical sessions covering the following subjects: National Regulatory Practices and Safety Standards (14 papers); Implementation of Regulatory Practices - Technical Issues (8 papers); Implementation of Regulatory Practices - Operational Aspects (8 papers); Developments and Trends in Safety Standards and Practices (11 papers); International Aspects (10 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  16. A Korean radioecology model to simulate radionuclide behavior in agricultural ecosystems following a nuclear emergency and its application to countermeasures

    International Nuclear Information System (INIS)

    Hwang, W.T.; Suh, K.S.; Kim, E.H.; Han, M.H.; Lee, H.S.; Lee, C.W.

    2003-01-01

    A Korean radioecology model to simulate radionuclide behavior in agricultural ecosystems has been developed as a module for evaluating the ingestion dose in a Korean real-time dose assessment system FADAS, which evaluates the comprehensive radiological consequences in an accidental release of radionuclides to the environment. Using the predictive results of a Korean radioecology model, a methodology for the optimization of countermeasures has been designed based on a cost-benefit analysis. In this manuscript, a Korean radioecology model including agricultural countermeasures was introduced, and discussed with the sample calculations for the postulated accidental release of radionuclides to the environment. (author)

  17. Mock Referendum on Nuclear Power with Korean Elementary, Middle, and High School Students

    International Nuclear Information System (INIS)

    Lee, Seung Koo; Park, Pil Han; Choi, Yoon Seok; Han, Eun Ok

    2017-01-01

    Today, policies relating to nuclear power generation face a myriad of issues regarding the aspects of understanding, sympathy, acceptance, and satisfaction by policy consumers. This study has provided education on nuclear power for elementary, middle, and high school students who are expected to have high ripple effects of communication and education, and organized a mock referendum on nuclear power generation to observe the results of the referendum. Based on the results of this study, it is important to provide sufficient information on the dangers of nuclear power to the future generation in order to enable them to participate in policies with the right value judgments. Both before and after the educational program, all of elementary, middle, and high school students overwhelmingly indicated that nuclear power was dangerous in presenting their disagreement. The expert groups must consider that students are concerned about the risks of nuclear power generation, despite the explanations from experts on the safety of nuclear power. Based on the results of this study, it is important to provide sufficient information on the dangers of nuclear power to the future generation in order to enable them to participate in policies with the right value judgments. Both before and after the educational program, all of elementary, middle, and high school students overwhelmingly indicated that nuclear power was dangerous in presenting their disagreement.

  18. Mock Referendum on Nuclear Power with Korean Elementary, Middle, and High School Students

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seung Koo; Park, Pil Han; Choi, Yoon Seok; Han, Eun Ok [Dept. of Education and Research, Korea Academy of Nuclear Safety, Seoul (Korea, Republic of)

    2017-04-15

    Today, policies relating to nuclear power generation face a myriad of issues regarding the aspects of understanding, sympathy, acceptance, and satisfaction by policy consumers. This study has provided education on nuclear power for elementary, middle, and high school students who are expected to have high ripple effects of communication and education, and organized a mock referendum on nuclear power generation to observe the results of the referendum. Based on the results of this study, it is important to provide sufficient information on the dangers of nuclear power to the future generation in order to enable them to participate in policies with the right value judgments. Both before and after the educational program, all of elementary, middle, and high school students overwhelmingly indicated that nuclear power was dangerous in presenting their disagreement. The expert groups must consider that students are concerned about the risks of nuclear power generation, despite the explanations from experts on the safety of nuclear power. Based on the results of this study, it is important to provide sufficient information on the dangers of nuclear power to the future generation in order to enable them to participate in policies with the right value judgments. Both before and after the educational program, all of elementary, middle, and high school students overwhelmingly indicated that nuclear power was dangerous in presenting their disagreement.

  19. Report on ANSI/ASME nuclear air and gas treatment standards for nuclear power plants

    International Nuclear Information System (INIS)

    Fish, J.F.

    1979-01-01

    Original N Committee, N45-8, has completed and published through the approved American National Standards Institute process two Standards, N-509 and N-510. This committee has been dissolved and replaced by ASME Committee on Nuclear Air and Gas Treatment with expanded scope to cover not only air cleaning, but thermal treatment equipment. Current efforts are directed to produce Code documents rather than Standards type publications. This report summarizes changed scope, current organization and sub-committee coverage areas

  20. European standards and approaches to EMC in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Bardsley, D.J.; Dillingham, S.R.; McMinn, K. [AEA Technology, Dorset (United Kingdom)

    1995-04-01

    Electromagnetic Interference (EMI) arising from a wide range of sources can threaten nuclear power plant operation. The need for measures to mitigate its effects have long been recognised although there are difference in approaches worldwide. The US industry approaches the problem by comprehensive site surveys defining an envelope of emissions for the environmental whilst the UK nuclear industry defined many years ago generic levels which cover power station environments. Moves to standardisation within the European community have led to slight changes in UK approach, in particular how large systems can be tested. The tests undertaken on UK nuclear plant include tests for immunity to conducted as well as radiated interference. Similar tests are also performed elsewhere in Europe but are not, to the authors` knowledge, commonly undertaken in the USA. Currently work is proceeding on draft international standards under the auspices of the IEC.

  1. Standard rules for liability and cover for nuclear installations

    International Nuclear Information System (INIS)

    Pfaffelhuber, J.K.; Kuckuck, B.

    1980-01-01

    To afford full protection for possible victims, the authors of this article are in favour of doing away with the limitation of liability of nuclear operators presently provided under the German Atomic Energy Act, the principle of which is based on the Paris Convention and the Brussels Supplementary Convention. In support of this argument reference is made to the recent accident at Three Mile Island, trends in other national legislation towards unlimited liability as well as high safety standards in German nuclear plants. Finally, possible ways of providing unlimited liability are proposed, in particular increased insurance cover and the constitution of an interest-bearing fund in addition to State intervention in case of a major nuclear incident. (NEA) [fr

  2. Domestic and International Nuclear Energy Voluntary Consensus Standards Needs

    International Nuclear Information System (INIS)

    Hopper, Calvin Mitchell

    2013-01-01

    This report introduces the reader to the domestic and international standards development organizations (SDOs) and their structures and operations. It also identifies some of the support and subject matter needs for the development of standards on the subject of nuclear energy. The support needs are described with regard to organizational structure and subject-matter-expert (SME) participation that is required for producing voluntary consensus standards. The subject matter needs are described with regard to growing technologies and objectives that approach the boundaries of existing standards; implementation of knowledge; and safety of people, facilities, and the environment. Standards are proposed, developed, and produced by SMEs with the support of industry and government organizations. The voluntary consensus standards development process is, as its name implies, a voluntary effort. The problem in today's competitive market, impacted by global economic uncertainty, is that the voluntary participation is shifting from a collaborative industry and SME effort to a nearly SME-only one. This shift places a financial and/or time burden on the SMEs to the point that they are purposely withdrawing from the standards development process, both domestically and internationally. The standards development process desperately needs participation from more and younger SMEs. The report includes several suggestions on how this can be addressed.

  3. Nuclear data standards - International Evaluation Co-operation volume 7

    International Nuclear Information System (INIS)

    Carlson, A.D.; Shibata, K.; Vonach, H.; Hambsch, F.J.; Chen, Z.; Hofmann, H.M.; Oh, S.Y.; Badikov, S.A.; Gai, E.V.; Pronyaev, V.G.; Smith, D.L.; Hale, G.M.; Kawano, T.; Larson, N.M.

    2006-01-01

    A Working Party on International Evaluation Co-operation was established under the sponsorship of the OECD/NEA Nuclear Science Committee (NSC) to promote the exchange of information on nuclear data evaluations, validation and related topics. Its aim is also to provide a framework for co-operative activities between members of the major nuclear data evaluation projects. This includes the possible exchange of scientists in order to encourage co-operation. Requirements for experimental data resulting from this activity are compiled. The working party determines common criteria for evaluated nuclear data files with a view to assessing and improving the quality and completeness of evaluated data. The parties to the project are: ENDF (United States), JEFF/EFF (NEA Data Bank member countries) and JENDL (Japan). Co-operation with evaluation projects of non-OECD countries is organised through the Nuclear Data Section of the International Atomic Energy Agency (IAEA). This report was issued by Subgroup 7, which was in charge of producing new evaluated neutron cross-section standards. When starting the project, there was a general consensus on the need to update these standards, as significant improvements had been made to the experimental database since 1991 when the last evaluation of these standards was performed. The present work was accomplished through efficient collaboration between a task force of the US Cross-section Evaluation Working Group (CSEWG), a Co-ordinated Research Project (CRP) of the International Atomic Energy Agency (IAEA) and Subgroup 7 of the Working Party on International Evaluation Co-operation (WPEC) of the NEA Nuclear Science Committee. Work is reported on the results of an international effort to evaluate the neutron cross-section standards. The evaluations include the H(n,n), 6 Li(n,t), 10 B(n,α), 10 B(n,α1γ), 197 Au(n,γ), 235 U(n,f) and 238 U(n,f) standard reactions. Evaluations were also produced for the non-standard 238 U(n,γ) and 239 Pu

  4. ASME Section XI trends in developing nuclear codes and standards

    International Nuclear Information System (INIS)

    Hedden, O.F.

    1995-01-01

    When the author began working on nuclear power many years ago, he knew that perfection was the only acceptable technical standard. Unfortunately, this became an obsession with perfection that has had unfavorable consequences in some of the non-technical areas of work in ASME nuclear power Codes and Standards. However, the economic problems of the nuclear power industry now demand a more pragmatic approach if the industry is to continue. Not only does each item considered for action need to be evaluated to criteria that may in some cases be less than perfection, but one needs to consider whether it contributes tangibly to either safety or to reduction in technical or administrative burden. These should be the governing, criteria. The introduction of risk-based inspection methodologies will certainly be an important element in doing this successfully. One needs to consider these criteria collectively, as one discusses each item at the committee level, and individually, as one votes on each item. In the past, the author has been concerned that the industry was not acting quickly enough in taking advantage of opportunities offered by the Code to increase safety or to reduce cost. While he still has some concern, he thinks communication channels have been greatly improved. Now he is becoming more concerned with both the collective and individual actions that delay beneficial changes. The second part of the author's talk has to do with the relevance of the code committees in the nuclear power industry regulatory process

  5. Regulatory Endorsement Activities for ASME Nuclear Codes and Standards

    International Nuclear Information System (INIS)

    West, Raymond A.

    2006-01-01

    The ASME Board on Nuclear Codes and Standards (BNCS) has formed a Task Group on Regulatory Endorsement (TG-RE) that is currently in discussions with the United States Nuclear Regulatory Commission (NRC) to look at suggestions and recommendations that can be used to help with the endorsement of new and revised ASME Nuclear Codes and Standards (NC and S). With the coming of new reactors in the USA in the very near future we need to look at both the regulations and all the ASME NC and S to determine where we need to make changes to support these new plants. At the same time it is important that we maintain our operating plants while addressing ageing management needs of our existing reactors. This is going to take new thinking, time, resources, and money. For all this to take place the regulations and requirements that we use must be clear concise and necessary for safety and to that end both the NRC and ASME are working together to make this happen. Because of the influence that the USA has in the world in dealing with these issues, this paper is written to inform the international nuclear engineering community about the issues and what actions are being addressed under this effort. (author)

  6. South Korean energy scenarios show how nuclear power can reduce future energy and environmental costs

    International Nuclear Information System (INIS)

    Hong, Sanghyun; Bradshaw, Corey J.A.; Brook, Barry W.

    2014-01-01

    South Korea is an important case study for understanding the future role of nuclear power in countries with on-going economic growth, and limited renewable energy resources. We compared quantitatively the sustainability of two ‘future-mapping’ exercises (the ‘Governmental’ scenario, which relies on fossil fuels, and the Greenpeace scenario, which emphasises renewable energy and excludes nuclear power). The comparison was based on a range of environmental and technological perspectives, and contrasted against two additional nuclear scenarios that instead envisage a dominant role for nuclear energy. Sustainability metrics included energy costs, external costs (greenhouse-gas emissions, air pollutants, land transformation, water consumption and discharge, and safety) and additional costs. The nuclear-centred scenarios yielded the lowest total cost per unit of final energy consumption by 2050 ($14.37 GJ −1 ), whereas the Greenpeace scenario has the highest ($25.36 GJ −1 ). We used probabilistic simulations based on multi-factor distributional sampling of impact and cost metrics to estimate the overlapping likelihoods among scenarios to understand the effect of parameter uncertainty on the integrated recommendations. Our simulation modelling implies that, despite inherent uncertainties, pursuing a large-scale expansion of nuclear-power capacity offers the most sustainable pathway for South Korea, and that adopting a nuclear-free pathway will be more costly and produce more greenhouse-gas emissions. - Highlights: • Nuclear power has a key role to play in mitigating greenhouse-gas emissions. • The Greenpeace scenario has higher total external cost than the nuclear scenarios. • The nuclear-centred scenarios offer the most sustainable option for South Korea. • The similar conclusions are likely to apply to other Asian countries

  7. Cross-cultural adaptation of the US consumer form of the short Primary Care Assessment Tool (PCAT): the Korean consumer form of the short PCAT (KC PCAT) and the Korean standard form of the short PCAT (KS PCAT).

    Science.gov (United States)

    Jeon, Ki-Yeob

    2011-01-01

    primary care in Korea. It will be used to identify any aspects of primary care linked to better or worse health outcomes, and to provide evidence-based evaluations of or recommendations for Korean healthcare policy. cross-cultural adaptation, Korean Standard Primary Care Assessment Tool, Primary Care Assessment Tool, quality of primary care.

  8. The Evolution of the North Korean Nuclear Crisis: Implications for Iran

    International Nuclear Information System (INIS)

    Chung Min, Lee

    2009-01-01

    The world today is confronted by North Korea that has apparently acquired successfully nuclear weapons, and by Iran that seems bent on acquiring, at a minimum, a virtual nuclear weapons capability. This trend suggests that prospects for freezing, if not rolling back, both Iran's and North Korea's programs are becoming increasingly difficult prospects. While President George W. Bush came under attack for going to war with Iraq based on faulty intelligence assessments and also for labeling Iran, Iraq and North Korea as part of the 'axis of evil', it cannot be denied that the world's 'most dangerous states with the most dangerous weapons' remain one of the defining security challenges of the post-9/11 era. Nevertheless, the Bush Administration's efforts to prevent, and failing that, to minimize the fallout from a nuclearized North Korea and a potentially nuclear capable Iran, have been decidedly mixed. Although North Korea maintained nuclear ambiguity for two decades, it finally gave up the pretense of having a 'virtual nuclear weapons program' in October 2006 whereas Iran continues on the path of nuclear brinkmanship. Whether Iran is going to cross the nuclear Rubicon remains uncertain but the fact that it has the requisite technologies and the political will to cross the nuclear threshold if it chose to do so remains unchanged. Regardless of Tehran's ultimate choice and attendant strategic consequences, Iran cannot but have gained key glimpses and insights from North Korea's decades-long pursuit of nuclear weapons. While Iran and North Korea have vastly different political histories and national ideologies, their paths have criss-crossed on the road towards nuclearization. Tehran and Pyongyang are not 'natural' allies although Iran has benefited from North Korea's ballistic missile sales (such as the Shahab-3 long-range missile). For its part, Pyongyang has gained not only from missile exports to Iran, but perhaps more significantly, by Iran's own nuclear challenge

  9. The Evolution of the North Korean Nuclear Crisis: Implications for Iran

    Energy Technology Data Exchange (ETDEWEB)

    Chung Min, Lee

    2009-07-01

    The world today is confronted by North Korea that has apparently acquired successfully nuclear weapons, and by Iran that seems bent on acquiring, at a minimum, a virtual nuclear weapons capability. This trend suggests that prospects for freezing, if not rolling back, both Iran's and North Korea's programs are becoming increasingly difficult prospects. While President George W. Bush came under attack for going to war with Iraq based on faulty intelligence assessments and also for labeling Iran, Iraq and North Korea as part of the 'axis of evil', it cannot be denied that the world's 'most dangerous states with the most dangerous weapons' remain one of the defining security challenges of the post-9/11 era. Nevertheless, the Bush Administration's efforts to prevent, and failing that, to minimize the fallout from a nuclearized North Korea and a potentially nuclear capable Iran, have been decidedly mixed. Although North Korea maintained nuclear ambiguity for two decades, it finally gave up the pretense of having a 'virtual nuclear weapons program' in October 2006 whereas Iran continues on the path of nuclear brinkmanship. Whether Iran is going to cross the nuclear Rubicon remains uncertain but the fact that it has the requisite technologies and the political will to cross the nuclear threshold if it chose to do so remains unchanged. Regardless of Tehran's ultimate choice and attendant strategic consequences, Iran cannot but have gained key glimpses and insights from North Korea's decades-long pursuit of nuclear weapons. While Iran and North Korea have vastly different political histories and national ideologies, their paths have criss-crossed on the road towards nuclearization. Tehran and Pyongyang are not 'natural' allies although Iran has benefited from North Korea's ballistic missile sales (such as the Shahab-3 long-range missile). For its part, Pyongyang has gained not only from missile

  10. Harmonization of nuclear codes and standards, pacific nuclear council working and task group report

    International Nuclear Information System (INIS)

    Dua, S.S.

    2006-01-01

    Full text: The codes and standards, both at the national and international level, have had a major impact on the industry worldwide and served it well in maintaining the performance and safety of the nuclear reactors and facilities. The codes and standards, in general, are consensus documents and do seek public input at various levels before they are finalized and rolled out for use by the nuclear vendors, consultants, utilities and regulatory bodies. However, the extensive development of prescriptive national standards if unchecked against the global environment and trade agreements (NAFTA, WTO, etc.) can also become barriers and cause difficulties to compete in the world market. During the last decade, the national and international writing standards writing bodies have recognized these issues and are moving more towards the rationalization and harmonization of their standards with the more widely accepted generic standards. The Pacific Nuclear Council (PNC) recognized the need for harmonization of the nuclear codes and standards for its member countries and formed a Task Group to achieve its objectives. The Task Group has a number of members from the PNC member countries. In 2005 PNC further raised the importance of this activity and formed a Working Group to cover a broader scope. The Working Group (WG) mandate is to identify and analyze the different codes and standards introduced to the Pacific Basin region, in order to achieve mutual understanding, harmonization and application in each country. This o requires the WG to develop and encourage the use of reasonably consistent criteria for the design and development, engineering, procurement, fabrication, construction, testing, operations, maintenance, waste management, decommissioning and the management of the commercial nuclear power plants in the Pacific Basin so as to: Promote consistent safety, quality, environmental and management standards for nuclear energy and other peaceful applications of nuclear

  11. Analysis of World Nuclear Market and Strategy of Korean NPP's Competitiveness Improvement for Exportation

    International Nuclear Information System (INIS)

    Choi, Jae Young; Jeong, Yong Hoon; Roh, Seungkook; Chang, Soon Heung

    2016-01-01

    China, India and USA (nuclear adopted countries) are planning tremendous number of NPPs to meet their increasing electricity demand and Saudi Arabia, Vietnam (nuclear adopting countries) are also planning to include nuclear power in their energy mix as a long-term plan. Korea has exported 4 units of APR1400 to the UAE in December, 2009. Korea became sixth NPP supplier country and our economic feasibility and safety features were started to evaluate worldwide. Nuclear industries became a new driver of Korea’s export and nuclear industries in Korea are now expecting another NPP export to Middle-eastern countries, including UAE and Saudi Arabia, based on the first-mover’s advantage at the UAE. In 2000s, five countries (Japan, USA, France, Russia and Korea), which are able to build NPP, focused on NPP export more than domestic construction. Global trend of world nuclear market changed rapidly, especially after NPP export to the UAE. By the global trend, hegemony of nuclear market migrated from supplier country to buyer country. Nuclear companies started cooperating rather than competing. Financing to developing countries become more important. In general, one of the considerable combinations is Korea-Japan-USA alliance. Korea is in charge of EPC, Japan supports financing and deficient technology (with USA partner), and Japan-USA handles fuel supply and back-end fuel cycle based on new agreed terms of ROK-US Nuclear Cooperation Agreement. This combination was judged to best way to collaborate with global companies. Paying attention to many delayed (or potentially delayed) constructions from Russia, intercepting the construction work will be available in case of contracted countries. Korea can emphasize the short construction time, high responsiveness and mild/equal diplomatic position to the target countries

  12. Harmonization of nuclear codes and standards. Pacific nuclear council working and task group report

    International Nuclear Information System (INIS)

    Dua, Shami

    2008-01-01

    Nuclear codes and standards have been an integral part of the nuclear industry since its inception. As the industry came into the main stream over the 2nd half of the 20th century, a number of national and international standards were developed to support a specific nuclear reactor concept. These codes and standards have been a key component of the industry to maintain its focus on nuclear safety, reliability and quality. Both national and international standards have served the industry well in obtaining public, shareholder and regulatory acceptance. The existing suite of national and international standards is required to support the emerging nuclear renaissance. However as noted above under Pacific Nuclear Council (PNC), Manufacturing Design Evaluation Program (MDEP) and SMiRT discussions, the time has come now for the codes and standards writing bodies and the industry to take the next step to examine the relevance of existing suite in view of current needs and challenges. This review must account for the changing global environment including global supply chain and regulatory framework, resources, deregulation, free trade, and industry need for competitiveness and performance excellence. The Task Group (TG) has made limited progress in this review period as no additional information on the listing of codes and standards have been received from the members. However, TG Chair has been successful in obtaining considerable interest from some additional individuals from the member countries. It is important that PNC management seek additional participation from the member countries and asks for their active engagement in the Working Group (WG) TG activities to achieve its mandate and deliverables. The harmonization of codes and standards is a key area for the emerging nuclear renaissance and as noted by a number of international organizations (refer to MDEP action noted above) that these tasks can not be completed unless we have the right level of resources and

  13. Thermal characteristics of spent activated carbon generated from air cleaning units in korean nuclear power plants

    Directory of Open Access Journals (Sweden)

    Ji-Yang So

    2017-06-01

    Full Text Available To identify the feasibility of disposing of spent activated carbon as a clearance level waste, we performed characterization of radioactive pollution for spent activated carbon through radioisotope analysis; results showed that the C-14 concentrations of about half of the spent activated carbon samples taken from Korean NPPs exceeded the clearance level limit. In this situation, we selected thermal treatment technology to remove C-14 and analyzed the moisture content and thermal characteristics. The results of the moisture content analysis showed that the moisture content of the spent activated carbon is in the range of 1.2–23.9 wt% depending on the operation and storage conditions. The results of TGA indicated that most of the spent activated carbon lost weight in 3 temperature ranges. Through py-GC/MS analysis based on the result of TGA, we found that activated carbon loses weight rapidly with moisture desorption reaching to 100°C and desorbs various organic and inorganic carbon compounds reaching to 200°C. The result of pyrolysis analysis showed that the experiment of C-14 desorption using thermal treatment technology requires at least 3 steps of heat treatment, including a heat treatment at high temperature over 850°C, in order to reduce the C-14 concentration below the clearance level.

  14. Thermal characteristics of spent activated carbon generated from air cleaning units in Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Hang Rae; So, Ji Yang [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2017-06-15

    To identify the feasibility of disposing of spent activated carbon as a clearance level waste, we performed characterization of radioactive pollution for spent activated carbon through radioisotope analysis; results showed that the C-14 concentrations of about half of the spent activated carbon samples taken from Korean NPPs exceeded the clearance level limit. In this situation, we selected thermal treatment technology to remove C-14 and analyzed the moisture content and thermal characteristics. The results of the moisture content analysis showed that the moisture content of the spent activated carbon is in the range of 1.2–23.9 wt% depending on the operation and storage conditions. The results of TGA indicated that most of the spent activated carbon lost weight in 3 temperature ranges. Through py-GC/MS analysis based on the result of TGA, we found that activated carbon loses weight rapidly with moisture desorption reaching to 100°C and desorbs various organic and inorganic carbon compounds reaching to 200°C. The result of pyrolysis analysis showed that the experiment of C-14 desorption using thermal treatment technology requires at least 3 steps of heat treatment, including a heat treatment at high temperature over 850°C, in order to reduce the C-14 concentration below the clearance level.

  15. Korean Unification: Opportunities and Threats

    National Research Council Canada - National Science Library

    Bundy, Richard B

    1992-01-01

    .... in addition, they agreed to support the Korean peninsula as a nuclear free zone. The two countries have existed in fact since the partition of the peninsula after the allied victory over Japan In 1945...

  16. Update to nuclear data standards for nuclear measurements. Summary report of a consultants` meeting

    Energy Technology Data Exchange (ETDEWEB)

    Wienke, H. [ed.; International Atomic Energy Agency, Vienna (Austria). Nuclear Data Section; Carlson, A. D. [National Inst. of Standards and Technology, Gaithersburg, MD (United States); Chiba, S. [Japan Atomic Energy Research Inst., Tokai (Japan); Hambsch, F. J. [Institute for Reference Materials and Measurements, Geel (Belgium); Olsson, N. [Department of Neutron Research, Uppsala Univ., Uppsala (Sweden); Smirnov, A. N. [V.G. Khlopin Radium Inst., St. Petersburg (Russian Federation)

    1997-05-01

    This document is an update of the 1991 NEANDC/INDC Nuclear Standards File (INDC(SEC)-101) to indicate the status and extension of cross section standards for the {sup 10}B(n,{alpha}) reaction in the energy region below 20 Mev; and the H(n,n), {sup 235}U9(n,f), {sup 238}U(n,f), and {sup 209}Bi(n,f) reactions for selected energy regions above 20 Mev. Refs, figs, tabs.

  17. Update to nuclear data standards for nuclear measurements. Summary report of a consultants' meeting

    International Nuclear Information System (INIS)

    Wienke, H.; Chiba, S.; Hambsch, F.J.; Olsson, N.; Smirnov, A.N.

    1997-05-01

    This document is an update of the 1991 NEANDC/INDC Nuclear Standards File (INDC(SEC)-101) to indicate the status and extension of cross section standards for the 10 B(n,α) reaction in the energy region below 20 Mev; and the H(n,n), 235 U9(n,f), 238 U(n,f), and 209 Bi(n,f) reactions for selected energy regions above 20 Mev. Refs, figs, tabs

  18. Introduction of Electrical System Simulation and Analysis Used in Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Sang Hak; Jeong, Woo Sung

    2015-01-01

    The purpose of this paper is to introduce the simulation methods and tools to analyse and predict the performance of the electric power distribution system for nuclear power plants (NPPs) in Korea. Electrical System design engineers are to evaluate the load flow, bus voltage profiles, short circuit levels, motor starting, and fast bus transfer under various plant operating conditions and to verify the adequacy of power distribution System for a reliable power supply to plant loads under various disturbances which could jeopardize a safe and reliable operation of nuclear power plants. (authors)

  19. Development of nuclear standard filter elements for PWR plant

    International Nuclear Information System (INIS)

    Weng Minghui; Wu Jidong; Gu Xiuzhang; Zhang Jinghua

    1988-11-01

    Model FRX-5 and FRX-10 nuclear standard filter elements are used for the fluid clarification of the chemical and volume control system (CVCS), boron recycle system (BRS), spent fuel pit cooling system (SFPCS) and steam generator blowdown system (SGBS) in Qinshan Nuclear Power Plant. The radioactive contaminant, fragment of resin and impurity are collected by these filter elements, The core of filter elements consists of polypropylene frames and paper filter medium bonded by resin. A variety of filter papers are tested for optimization. The flow rate and comprehensive performance have been measured in the simulation condition. The results showed that the performance and lifetime have met the designing requirements. The advantages of the filter elements are simple in manufacturing, less expense and facilities for waste-disposal. At present, some of filter elements have been produced and put in operation

  20. Nuclear station safety standardization from a risk concept

    International Nuclear Information System (INIS)

    Veksler, L.M.

    1986-01-01

    This paper presents a method of standardizing safety-system reliability on an entirely new basis: all hypothetical accidents are approximated as groups, for each of which one proposes permissible frequencies on the basis of the risk concept. In this risk concept, the ''average person'' is a person living near a nuclear station or working in it, who is of average age, average state of health, and so on. Therefore, the risk can be found by summing the estimated individual risks for a particular group in the population followed by division by the number of people in that group. Basic assumptions in deriving permissible safety-system reliability are presented. Estimated permissible failure probabilities are given to illustrate the proposed method and to refine the initial data. The probabilities may also be used to lay down the reliability requirements for safety systems in particular nuclear stations on the risk basis

  1. Standardized safety management of AP1000 nuclear power plant

    International Nuclear Information System (INIS)

    Li Xingwen; Cao Zhiqiang; Cong Jiuyuan

    2011-01-01

    In 2002, China published and implemented the Law of the People's Republic of China on Work Safety and promulgated a series of guidelines and policies, which strengthened the safety management supervision. Standardization of safety, as another important step on safety supervision, comes after safety assesment and safety production licensing system, is also a permanent solution. Standardization of safety is a strategic, long term and fundamental work, which is also the basic access to achieving scientific safety management and increasing the inherent safety of an enterprise. Haiyang AP1000 nuclear power plant, adopting the modularized, 'open-top' and parallel construction means, overturned the traditional construction theory of installation work comes after the civil work and greatly shorten the construction period. At the same time, the notable increase of oversize module transportation and lifting and parallel construction raises higher demands for safety management. This article combines the characteristics and difficulties of safety management for Haiyang AP1000 nuclear power plant, puts forward ideas and methods for standardized safety management, and could also serve as reference to the safety management for other AP1000 projects. (authors)

  2. Comparison of ISO 9000 and recent software life cycle standards to nuclear regulatory review guidance

    International Nuclear Information System (INIS)

    Preckshot, G.G.; Scott, J.A.

    1998-01-01

    Lawrence Livermore National Laboratory is assisting the Nuclear Regulatory Commission with the assessment of certain quality and software life cycle standards to determine whether additional guidance for the U.S. nuclear regulatory context should be derived from the standards. This report describes the nature of the standards and compares the guidance of the standards to that of the recently updated Standard Review Plan

  3. Nuclear Regulatory Commission and its role in environmental standards

    International Nuclear Information System (INIS)

    Mattson, R.J.

    1976-01-01

    The NRC and its predecessors in the Atomic Energy Commission represent considerable experience in environmental standards setting. The Atomic Energy Act of 1954, the 1970 Supreme Court decision on Federal pre-emption of radiation standards, the Calvert Cliffs decision of 1971, the Energy Reorganization Act of 1974, and the Appendix I ''as low as reasonably achievable'' decision of 1975, to name a few of our landmarks, are representative of the scars and the achievements of being in a role of national leadership in radiation protection. The NRC, through a variety of legislative authorities, administrative regulations, regulatory guides, and national consensus standards regulates the commercial applications of nuclear energy. The purposes of regulation are the protection of the environment, public health and safety, and national security. To understand NRC's responsibilities relative to those of other Federal and state agencies concerned with environmental protection, we will briefly review the legislative authorities which underlie our regulatory program. Then we will examine the intent or the spirit of that program as embodied in our system of regulations, guides, and standards. Finally we will speak to what's happening today and what we see in the future for environmental standards

  4. Role of radiation standards in peaceful uses of nuclear energy

    International Nuclear Information System (INIS)

    Mahant, A.K.; Sathian, V.; Joseph, L.

    2009-01-01

    Radiation standards play an acute role in all the peaceful applications of nuclear energy, which is not limited to generation of electrical power anymore. Radioactive sources are being used in a very wide variety of applications, which can be broadly classified as medicine, agriculture, industry and scientific research. All these applications involve the use of radiation in a well-controlled manner and hence require accurate characterization and quantification of the radiation. Radiation Standards Section of Radiation Safety Systems Division at BARC is the apex national laboratory for all the radiological quantities related to various types of radiation sources. The laboratory develops, maintains and disseminates the standards to the users of the radiation sources all over the country and some of the neighbouring countries viz. Nepal, Bangladesh, Sri Lanka and Myanmar with an essential objective to bring homogeneity in all radiological measurements and make them compatible with the international standards. Various services provided by the Radiation Standards Section have been briefly described in the following sections. (author)

  5. Study on Korean Radiological Emergency System-Care System- and National Nuclear Emergency Preparedness System Development

    International Nuclear Information System (INIS)

    Akhmad Khusyairi; Yudi Pramono

    2008-01-01

    Care system; Radiological Emergency Supporting System. Environmental radiology level is the main aspect that should be concerned deal with the utilization of nuclear energy. The usage of informational technology in nuclear area gives significant contribution to anticipate and to protect human and environment. Since 1960, South Korea has developed environment monitoring system as the effort to protect the human and environment in the radiological emergency condition. Indonesia has possessed several nuclear installations and planned to build and operate nuclear power plants (PLTN) in the future. Therefore, Indonesia has to prepare the integrated system, technically enables to overcome the radiological emergency. Learning from the practice in South Korea, the system on the radiological emergency should be prepared and applied in Indonesia. However, the government regulation draft on National Radiological Emergency System, under construction, only touches the management aspect, not the technical matters. Consequently, when the regulation is implemented, it will need an additional regulation on technical aspect including the consideration on the system (TSS), the organization of operator and the preparation of human resources development of involved institution. For that purpose, BAPETEN should have a typical independence system in regulatory frame work. (author)

  6. Advanced passive technology: A global standard for nuclear plant requirements

    International Nuclear Information System (INIS)

    Novak, V.

    1994-01-01

    Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy' (DOE). The preliminary design was cornpleved in 1989. AP6OO's Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance

  7. Knowledge management for assuring high standards in nuclear safety

    International Nuclear Information System (INIS)

    Hahn, L.

    2004-01-01

    The primary incentives for introducing knowledge management in organisations active in the nuclear field are the impending loss of knowledge due to an ageing workforce and the necessity to transfer knowledge to the next generation. However, knowledge management may reach much further, and it is shown that ultimately, the goals of knowledge management are congruent with establishing, maintaining and further developing high standards of safety. Knowledge-based activities to reach these goals are discussed, and examples given for producing, utilising and sharing knowledge in organisations and in national and international networks. (author)

  8. Nuclear design aspect of the Korean high intensity proton accelerator project

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Jonghwa; Song, Tae-Yung [Korea Atomic Energy Research Inst., Yusong, Taejon (Korea, Republic of)

    1998-11-01

    A plan to construct a high current proton accelerator has been proposed by KAERI. We are presenting the required nuclear design to support the project as well as a brief overview of the proposed proton accelerator. The target and core design is highlighted to show feasibility of incineration of minor actinides from the spent fuel of light water reactors. Radiation shielding and activation analyses are also important for the design and the license of the accelerator. (author)

  9. Investigations on human error hazards in recent unintended trip events of Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sa Kil; Jang, Tong Il; Lee, Yong Hee; Shin, Kwang Hyeon [KAERI, Daejeon (Korea, Republic of)

    2012-10-15

    According to the Operational Performance Information System (OPIS) which has been operated to improve the public understanding by the KINS (Korea Institute of Nuclear Safety), unintended trip events by mainly human errors counted up to 38 cases (18.7%) from 2000 to 2011. Although the Nuclear Power Plant (NPP) industry in Korea has been making efforts to reduce the human errors which have largely contributed to trip events, the human error rate might keep increasing. Interestingly, digital based I and C systems is the one of the reduction factors of unintended reactor trips. Human errors, however, have occurred due to the digital based I and C systems because those systems require new or changed behaviors to the NPP operators. Therefore, it is necessary that the investigations of human errors consider a new methodology to find not only tangible behavior but also intangible behavior such as organizational behaviors. In this study we investigated human errors to find latent factors such as decisions and conditions in the all of the unintended reactor trip events during last dozen years. To find them, we applied the HFACS (Human Factors Analysis and Classification System) which is a commonly utilized tool for investigating human contributions to aviation accidents under a widespread evaluation scheme. The objective of this study is to find latent factors behind of human errors in nuclear reactor trip events. Therefore, a method to investigate unintended trip events by human errors and the results will be discussed in more detail.

  10. Investigations on human error hazards in recent unintended trip events of Korean nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Sa Kil; Jang, Tong Il; Lee, Yong Hee; Shin, Kwang Hyeon

    2012-01-01

    According to the Operational Performance Information System (OPIS) which has been operated to improve the public understanding by the KINS (Korea Institute of Nuclear Safety), unintended trip events by mainly human errors counted up to 38 cases (18.7%) from 2000 to 2011. Although the Nuclear Power Plant (NPP) industry in Korea has been making efforts to reduce the human errors which have largely contributed to trip events, the human error rate might keep increasing. Interestingly, digital based I and C systems is the one of the reduction factors of unintended reactor trips. Human errors, however, have occurred due to the digital based I and C systems because those systems require new or changed behaviors to the NPP operators. Therefore, it is necessary that the investigations of human errors consider a new methodology to find not only tangible behavior but also intangible behavior such as organizational behaviors. In this study we investigated human errors to find latent factors such as decisions and conditions in the all of the unintended reactor trip events during last dozen years. To find them, we applied the HFACS (Human Factors Analysis and Classification System) which is a commonly utilized tool for investigating human contributions to aviation accidents under a widespread evaluation scheme. The objective of this study is to find latent factors behind of human errors in nuclear reactor trip events. Therefore, a method to investigate unintended trip events by human errors and the results will be discussed in more detail

  11. The 13 february action plan and the prospects for the North Korean nuclear issue

    International Nuclear Information System (INIS)

    Narushige, Muchishita

    2007-01-01

    On 13 February, the Third Session of the Fifth Round of the Six-Party Talks ended with the adoption of the 'Action Plan' for the implementation of the September 2005 Joint Statement.2 The Action Plan has two phases - the initial phase and the 'next' phase - but the core of the deal lies in the initial stage in which the parties agreed to exchange the nuclear freeze and the provision of energy. In the initial phase, North Korea will 'shut down and seal' the Yongbyon nuclear facility, including the reprocessing facility, and invite back International Atomic Energy Agency (IAEA) personnel to conduct monitoring and verifications within 60 days. In return, the other parties of the talks will provide emergency energy assistance equivalent to 50,000 tons of heavy fuel oil (HFO) to North Korea. There are other items in the initial stage such as North Korea discussing a list of all its nuclear programs with other parties, and the United States and North Korea starting bilateral talks toward full diplomatic relations. However, these items are rather nominal and symbolic in nature and will not likely produce meaningful results in a short period of time. The second phase is even more open-ended. In the second phase, North Korea will provide a complete declaration of all nuclear programs and disable all existing nuclear facilities. In return, the other parties will provide economic, energy and humanitarian assistance up to the equivalent of 950,000 tons of HFO. However, the timing and the details of the nuclear 'disablement' and the provision of assistance are not specified, making it likely that the parties will disagree over how to interpret the words in the Action Plan. The Action Plan provides that five Working Groups (WG) on different topics will be established in order to discuss the details, but the effectiveness of the WG remains to be seen. The Action Plan, therefore, represents the lowest common denominator for the parties involved. In agreeing to the plan, all

  12. The 13 february action plan and the prospects for the North Korean nuclear issue

    Energy Technology Data Exchange (ETDEWEB)

    Narushige, Muchishita

    2007-07-01

    On 13 February, the Third Session of the Fifth Round of the Six-Party Talks ended with the adoption of the 'Action Plan' for the implementation of the September 2005 Joint Statement.2 The Action Plan has two phases - the initial phase and the 'next' phase - but the core of the deal lies in the initial stage in which the parties agreed to exchange the nuclear freeze and the provision of energy. In the initial phase, North Korea will 'shut down and seal' the Yongbyon nuclear facility, including the reprocessing facility, and invite back International Atomic Energy Agency (IAEA) personnel to conduct monitoring and verifications within 60 days. In return, the other parties of the talks will provide emergency energy assistance equivalent to 50,000 tons of heavy fuel oil (HFO) to North Korea. There are other items in the initial stage such as North Korea discussing a list of all its nuclear programs with other parties, and the United States and North Korea starting bilateral talks toward full diplomatic relations. However, these items are rather nominal and symbolic in nature and will not likely produce meaningful results in a short period of time. The second phase is even more open-ended. In the second phase, North Korea will provide a complete declaration of all nuclear programs and disable all existing nuclear facilities. In return, the other parties will provide economic, energy and humanitarian assistance up to the equivalent of 950,000 tons of HFO. However, the timing and the details of the nuclear 'disablement' and the provision of assistance are not specified, making it likely that the parties will disagree over how to interpret the words in the Action Plan. The Action Plan provides that five Working Groups (WG) on different topics will be established in order to discuss the details, but the effectiveness of the WG remains to be seen. The Action Plan, therefore, represents the lowest common denominator for the parties

  13. Nuclear power in Korea

    International Nuclear Information System (INIS)

    Rim, C.S.

    1990-01-01

    Before addressing the issue of public and utility acceptance of nuclear power in Korea, let me briefly explain the Korean nuclear power program and development plan for a passively safe nuclear power plant in Korea. At present, there are eight PWRs and one CANDU in operation; two PWRs are under construction, and contract negotiations are underway for one more CANDU and two more PWRs, which are scheduled to be completed by 1997,1998 and 1999, respectively. According to a recent forecast for electricity demand in Korea, about fifty additional nuclear power plants with a generating capacity of 1000MWe are required by the year 2030. Until around 2006, Korean standardized nuclear power plants with evolutionary features such as those in the ALWR program are to be built, and a new type of nuclear power plant with passive safety features is expected to be constructed after 2006. The Korean government is making a serious effort to increase public understanding of the safety of nuclear power plants and radioactive waste storage and disposal. In addition, the Korean government has recently introduced a program of benefits for residents near nuclear power plants. By this program, common facilities such as community centers and new roads are constructed, and scholarships are given to the local students. Nuclear power is accepted positively by the utility and reasonably well by the public in Korea

  14. Nuclear power in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Rim, C S [Radioactive Waste Management Centre, Korea Atomic Energy Research Institute, Taejon, Choong-Nam (Korea, Republic of)

    1990-07-01

    Before addressing the issue of public and utility acceptance of nuclear power in Korea, let me briefly explain the Korean nuclear power program and development plan for a passively safe nuclear power plant in Korea. At present, there are eight PWRs and one CANDU in operation; two PWRs are under construction, and contract negotiations are underway for one more CANDU and two more PWRs, which are scheduled to be completed by 1997,1998 and 1999, respectively. According to a recent forecast for electricity demand in Korea, about fifty additional nuclear power plants with a generating capacity of 1000MWe are required by the year 2030. Until around 2006, Korean standardized nuclear power plants with evolutionary features such as those in the ALWR program are to be built, and a new type of nuclear power plant with passive safety features is expected to be constructed after 2006. The Korean government is making a serious effort to increase public understanding of the safety of nuclear power plants and radioactive waste storage and disposal. In addition, the Korean government has recently introduced a program of benefits for residents near nuclear power plants. By this program, common facilities such as community centers and new roads are constructed, and scholarships are given to the local students. Nuclear power is accepted positively by the utility and reasonably well by the public in Korea.

  15. Practical standard for nuclear power plant life management programs: 2007

    International Nuclear Information System (INIS)

    2006-03-01

    The standard specifies the method of implementing nuclear power plant life management programs. The plant life management programs evaluate the integrity of the plant structures, systems and components, assessing if appropriate measures are taken against existing aging phenomena, if there are possibilities of occurrence and development of aging phenomena and if a sufficient level of margin is maintained to assure the integrity throughout the future operating period. The programs also assess the validity of the current maintenance activities, such as trend monitoring, walkdowns, periodic tests and inspections, repair and replacement work for the purpose of preventive maintenance, and utilization of lessons learned from past trouble experience, in order to newly identify maintenance measures. The technical evaluation on aging phenomena is conducted to establish the 10 year maintenance program for nuclear power plants until the plant reaches 30 years of service. The standard was established and issued by the Atomic Energy Society of Japan (AESJ) through the discussion of experts in the associated fields. (T. Tanaka)

  16. Development of the software for the component reliability database system of Korean nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Han, Sang Hoon; Kim, Seung Hwan; Choi, Sun Young [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2002-03-01

    A study was performed to develop the system for the component reliability database which consists of database system to store the reliability data and softwares to analyze the reliability data.This system is a part of KIND (Korea Information System for Nuclear Reliability Database).The MS-SQL database is used to stores the component population data, component maintenance history, and the results of reliability analysis. Two softwares were developed for the component reliability system. One is the KIND-InfoView for the data storing, retrieving and searching. The other is the KIND-CompRel for the statistical analysis of component reliability. 4 refs., 13 figs., 7 tabs. (Author)

  17. Nuclear E&T for Building and Sustaining Capacity from Korean Experience

    International Nuclear Information System (INIS)

    Nam, Youngmi

    2014-01-01

    Lessons learned: • A strong national initiative needs to be maintained, involving stakeholders with a staged national nuclear E&T plan and its execution together with an HRD plan. • An integrated competence based E&T for NEPIOs, operators, regulators, TSOs and etc. is an important element to become a knowledgeable customer or responsible vendor. • International cooperation is a useful mechanism by which long-term and widely ranged experience from others, including international organizations can be absorbed or transferred effectively in a relatively shorter term, minimizing trial and error

  18. Nuclear microprobe analysis of the standard reference materials

    International Nuclear Information System (INIS)

    Jaksic, M.; Fazinic, S.; Bogdanovic, I.; Tadic, T.

    2002-01-01

    Most of the presently existing Standard Reference Materials (SRM) for nuclear analytical methods are certified for the analyzed mass of the order of few hundred mg. Typical mass of sample which is analyzed by PIXE or XRF methods is very often below 1 mg. By the development of focused proton or x-ray beams, masses which can be typically analyzed go down to μg or even ng level. It is difficult to make biological or environmental SRMs which can give desired homogeneity at such low scale. However, use of fundamental parameter quantitative evaluation procedures (absolute method), minimize needs for SRMs. In PIXE and micro PIXE setup at our Institute, fundamental parameter approach is used. For exact calibration of the quantitative analysis procedure just one standard sample is needed. In our case glass standards which showed homogeneity down to micron scale were used. Of course, it is desirable to use SRMs for quality assurance, and therefore need for homogenous materials can be justified even for micro PIXE method. In this presentation, brief overview of PIXE setup calibration is given, along with some recent results of tests of several SRMs

  19. Is China Still a Viable Mediator to Solve the North Korean Nuclear Problem?

    Directory of Open Access Journals (Sweden)

    Eunsook Yang

    2006-10-01

    Full Text Available China se unió a la resolución de la ONU reclamando sanciones económicas contra Corea del Norte en protesta por su lanzamiento de un misil el 5 de Julio y por su prueba nuclear del 9 de octubre. Esta posición contrastaba con su pasada oposición a las sanciones a Corea del Norte. China no cambiaría sus principios en las relaciones con Corea del Norte debido a sus propios intereses de seguridad en la península coreana. No obstante, China se vio obligada a asumir un papel de mediadora en la comunidad internacional y dar una lección a su problemático aliado norcoreano.

  20. External Cost Assessment of Nuclear Power Plant Accident considering Public Risk Aversion Behavior: the Korean Case

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Hun; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    The conventional approach for monetary valuation of NPP accident consequence consists of calculating the expected value of various accident scenarios. However, the main criticism of the conventional approach is that there is a discrepancy between the social acceptability of the risk and the estimated expected value of NPP accident. Therefore, an integrated framework for the estimation of the external cost associated with an NPP accident considering the public risk aversion behavior was proposed in this study based on the constructed theoretical framework for estimating both the value of statistical life (VSL) and the risk aversion coefficient associated with an NPP accident to take account of the accident cost into the unit electricity generation cost of NPP. To estimate both parameters, an individual-level survey was conducted on a sample of 1,364 participants in Korea. Based on the collected survey responses, both parameters were estimated based on the proposed framework and the external cost of NPP accident was estimated based on the consequence analysis and considering the direct cost factors for NPP accident. Internalization of external costs into the comprehensive energy production cost has been considered as a potentially efficient policy instrument for a more sustainable energy supply and use. However, the internalization of externalities, such as public health damage, have raised a number of generic policy issues in a nuclear energy sector, with specific challenges resulting from the distinct characteristics of external cost estimation. Especially, the major challenge remained to address the public safety concerns regarding a nuclear accident, which can be specified as low-probability high-consequence accident, driven by the aspects of public risk aversion.

  1. External Cost Assessment of Nuclear Power Plant Accident considering Public Risk Aversion Behavior: the Korean Case

    International Nuclear Information System (INIS)

    Lee, Sang Hun; Kang, Hyun Gook

    2016-01-01

    The conventional approach for monetary valuation of NPP accident consequence consists of calculating the expected value of various accident scenarios. However, the main criticism of the conventional approach is that there is a discrepancy between the social acceptability of the risk and the estimated expected value of NPP accident. Therefore, an integrated framework for the estimation of the external cost associated with an NPP accident considering the public risk aversion behavior was proposed in this study based on the constructed theoretical framework for estimating both the value of statistical life (VSL) and the risk aversion coefficient associated with an NPP accident to take account of the accident cost into the unit electricity generation cost of NPP. To estimate both parameters, an individual-level survey was conducted on a sample of 1,364 participants in Korea. Based on the collected survey responses, both parameters were estimated based on the proposed framework and the external cost of NPP accident was estimated based on the consequence analysis and considering the direct cost factors for NPP accident. Internalization of external costs into the comprehensive energy production cost has been considered as a potentially efficient policy instrument for a more sustainable energy supply and use. However, the internalization of externalities, such as public health damage, have raised a number of generic policy issues in a nuclear energy sector, with specific challenges resulting from the distinct characteristics of external cost estimation. Especially, the major challenge remained to address the public safety concerns regarding a nuclear accident, which can be specified as low-probability high-consequence accident, driven by the aspects of public risk aversion

  2. Infrasound Observation of the Apparent North Korean Nuclear Test of 25 May 2009

    Science.gov (United States)

    Jeon, J.; Che, I.; Kim, T.; Lee, H.

    2009-12-01

    On 25 May 2009, a seismic event (mb 4.6) was recorded from a source in northeastern North Korea, close to the location of a previous seismic event on 9 October 2006. Both events have been declared to be nuclear tests. Five seismo-acoustic arrays in South Korea recorded epicentral infrasonic signals for the more recent test following the strong seismic waves from the explosion. This study describes the characteristics of the nuclear test-generated infrasound signals observed at infrasound arrays located from 304 to 528 km from the source. The signals were characterized by stratospheric returns with amplitudes from 0.16 to 0.35 microbar and dominant frequencies between 1.0 and 4.3 Hz. Celerities determined for the arrivals suggest that most of the infrasonic energy travelled as a stratospheric phase. The inferred infrasonic location was offset about 15.7 km from the reference seismic location. On the basis of observed amplitudes of the stratospheric phases and corrections based on prevailing winds, the epicentral infrasonic energy was estimated to be equivalent to that expected from about 2.2 ton surface detonation of conventional explosives. We conclude that this small energy estimate is related to the partitioning of the contained explosive energy resulting from the interaction of strong ground motion at the surface with the atmosphere rather than the direct transfer of explosion energy to the air. This relatively small energy ratio between the infrasonic energy and the seismic energy could be used to distinguish the event from a common surface explosion.

  3. Advanced passive technology: A global standard for nuclear plant requirements

    Energy Technology Data Exchange (ETDEWEB)

    Novak, V

    1994-12-31

    Since 1984, Westinghouse has been developing AP8OO, a 800 MW, two-loop advanced passive plant, in response to an initiative established by the Electric Power Research Institute (EPRI) and the U.S. Department of Energy` (DOE). The preliminary design was cornpleved in 1989. AP6OO`s Standard Safety Analysis and Probabilistic Risk analysis Reports were submitted to the U.S. Nuclear Regulatory Commission for design certification in 1992. Design simplification is the key strategy behind the AP6OO. The basic technical concept Of simplification has resulted in a simplified reactor coolant systems, simplified plant systems, a simplified plant arrangement, reduced number of components, simplified operation and maintenance.

  4. Parameter Data on the Radiocesium Transfer to Korean Staple Food Crops Following a Nuclear Accident

    International Nuclear Information System (INIS)

    Choi, Yong-Ho; Lim, Kwang-Muk; Jun, In; Kim, Byung-Ho; Keum, Dong-Kwon

    2016-01-01

    In order to decide an optimum countermeasure against farmland contaminations following a severe NPP accident, it is necessary to have a reliable tool for predicting the concentrations of radiocesium in crop plants. For the estimation of radionuclide concentrations in crop plants, various transfer parameters, which quantify the radionuclide transfer from one compartment to the next, are used in general. Some amount of transfer parameter data has been produced at the Korea Atomic Energy Research Institute (KAERI) over the last 30 years. The present work was conducted to collate the KAERI data on radiocesium in staple food crops and to suggest effective ways of using them for assessing the environmental impact of a nuclear accident. The transfer parameter values of radiocesium for rice, Chinese cabbage and radish varied considerably with soils and times of its deposition. The proposed representative values were mostly based on a limited amount of data so they cannot be considered to have a high representativeness. Accordingly, they are intended for provisional use and a continuous improvement should be made. It is necessary to produce a sufficient amount of additional domestic data on the indirect pathway by conducting root-uptake experiments with as many types of soil as possible

  5. Parameter Data on the Radiocesium Transfer to Korean Staple Food Crops Following a Nuclear Accident

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Yong-Ho; Lim, Kwang-Muk; Jun, In; Kim, Byung-Ho; Keum, Dong-Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In order to decide an optimum countermeasure against farmland contaminations following a severe NPP accident, it is necessary to have a reliable tool for predicting the concentrations of radiocesium in crop plants. For the estimation of radionuclide concentrations in crop plants, various transfer parameters, which quantify the radionuclide transfer from one compartment to the next, are used in general. Some amount of transfer parameter data has been produced at the Korea Atomic Energy Research Institute (KAERI) over the last 30 years. The present work was conducted to collate the KAERI data on radiocesium in staple food crops and to suggest effective ways of using them for assessing the environmental impact of a nuclear accident. The transfer parameter values of radiocesium for rice, Chinese cabbage and radish varied considerably with soils and times of its deposition. The proposed representative values were mostly based on a limited amount of data so they cannot be considered to have a high representativeness. Accordingly, they are intended for provisional use and a continuous improvement should be made. It is necessary to produce a sufficient amount of additional domestic data on the indirect pathway by conducting root-uptake experiments with as many types of soil as possible.

  6. Referring to IAEA system to improve Chinese standards system on nuclear and radiation safety

    International Nuclear Information System (INIS)

    Shang Zhaorong; Wang Wenhai

    2010-01-01

    Referring to the standards system of IAEA, to build and improve the Chinese standards system of nuclear and radiation safety is a long term infrastructure work and an assurance to keep sustainable development of nuclear industry and nuclear technology application in China. The paper analyses the current main problem, and gives some suggestions on developing and improving the system. (authors)

  7. 76 FR 14437 - Economic Simplified Boiling Water Reactor Standard Design: GE Hitachi Nuclear Energy; Issuance of...

    Science.gov (United States)

    2011-03-16

    ... NUCLEAR REGULATORY COMMISSION [NRC-2011-0055] Economic Simplified Boiling Water Reactor Standard Design: GE Hitachi Nuclear Energy; Issuance of Final Design Approval The U.S. Nuclear Regulatory Commission has issued a final design approval (FDA) to GE Hitachi Nuclear Energy (GEH) for the economic...

  8. Application of Pressure Equipment Standard at nuclear power plants; Aplicacion del Reglamento de Equipos a Presion a las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Mostaza, J. M.

    2011-07-01

    Regarding with the paper presented on 9{sup t}h June 2011 referred to the Industrial Security standard in Nuclear Plants, it was about the application of Pressure Equipment standard to mentioned Nuclear Plants, this article is an extract of the paper going to be exposed. (Author)

  9. Licensing procedure, nuclear codes and standards in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Schultheiss, G.F.

    1980-01-01

    The present paper deals with legal background of licensing in nuclear technology and atomic energy use, licensing procedures for nuclear power plants and with codes, standards and guidelines in the Federal Republic of Germany. (orig./RW)

  10. Trace of Korean mechanical industry

    International Nuclear Information System (INIS)

    1996-12-01

    This book reports 50 years of Korean mechanical engineers, which includes birth and history, remembrance and future of Korean society of mechanical engineers, current situation and development of mechanical industry such as national industry and 50 years of mechanical industry, track, airline industry, ship and marine engine, a precision instrument, cutting work, casting, welding, plastic working freeze and air handling nuclear power and textile machinery.

  11. Principles and foundation: national standards on quantities and units in nuclear science field

    International Nuclear Information System (INIS)

    Chen Lishu

    1993-11-01

    The main contents of National Standards on Quantities and units of atomic and nuclear physics (GB 3102.9) and Quantities and Units of nuclear reactions and ionizing radiations (GB 310.10) are presented in which most important quantities with their symbols and definitions in the nuclear scientific field are given. The principles and foundation, including the International System of Units (SI) and its application to the nuclear scientific field, in the setting of the National Standards are explained

  12. Revision of the ASME nuclear quality assurance standard and its historical background

    International Nuclear Information System (INIS)

    Suzuki, Tetsuya

    2009-01-01

    ASME NQA-1-2008 'Quality Assurance Requirements for Nuclear Facility Applications' will be endorsed by US NRC by the end of 2009. This standard will apply to design, construction and operation of nuclear power plants newly erected in USA. It is important to Japanese vendors developing nuclear business in USA. Historical background, significance of revision and main revised points of the ASME nuclear quality assurance standard are described in the present paper. (T. Tanaka)

  13. Will nuclear power plant standardization reduce the licensing impact on construction

    International Nuclear Information System (INIS)

    Allen, J.M.; Bingham, W.G.; Keith, D.G.

    1976-01-01

    The NRC and the nuclear industry have been pursuing standardization quite vigorously in an effort to reduce the cost and schedule for the design and construction of nuclear power plants. The NRC is currently reviewing standard plant applications submitted under each of four standardization options. In addition, the NRC has published Standard Review Plans and Standard Technical Specifications. Although problems exist in the implementation of standardization and in areas unaffected by standardization, each of these standardization methods has the potential to reduce the licensing impact on construction

  14. A preliminary study on the design in architecture of nuclear and radiation safety standard system

    International Nuclear Information System (INIS)

    Song Dahu; Zhang Chi; Yang Lili; Li Bin; Liu Yingwei; An Hongzhen; Gao Siyi; Liu Ting; Meng De

    2014-01-01

    The connotation and function of nuclear and radiation safety standards are analyzed, and their relationships with the relevant laws and regulations are discussed in the paper. Some suggestions and blue print of overall architecture to build nuclear and radiation safety standard system are proposed, on the basis of researching the application status quo, existing problems and needs for nuclear and radiation safety standards in China. This work is a beneficial exploration and attempt to establish China's nuclear and radiation safety standards. (authors)

  15. AP1000 - the new standard for nuclear power

    International Nuclear Information System (INIS)

    Lipman, Daniel S.

    2006-01-01

    Full text of publication follows: The AP1000 is the only Generation III+ reactor to receive Final Design Approval (FDA) from the Nuclear Regulatory Commission, and is expected to receive its Design Certification by the end of the year. Building on the proven features of current generation nuclear plants, the AP1000 combines experience with innovation into a design that surpasses current standards of safety and reliability. Use of passive safety features results in a simpler and more compact design that enhances safety, simplifies O and M requirements, and reduces capital and operating costs. At 1117 Mwe, the AP1000 is well suited for almost any grid system and will be fully competitive with combined-cycle gas and comparable fossil fuel plants. The AP1000 is ready to help launch a renaissance in new nuclear plant construction throughout the world. Maturity of Design: In excess of 1300 man-years and $400 million in development funding have been expended on the AP1000. It has undergone extensive, part scale testing at the system, sub-system and component level, in addition to a series of part scale integrated tests. The AP1000 is the most analyzed of the next generation reactors. Simplicity of Design/Economics: The AP1000 uses simplified and innovative passive safety systems to an unprecedented extent. Simplified passive safety systems provide reliable operation, reduced capital costs, and enhanced plant safety with large plant operating margins. The AP1000 features improved reliability through simplicity rather than addition of redundant safety trains. This simpler design is easier and less costly to operate and maintain than larger, more complex plants, while less equipment and smaller buildings translate into lower capital costs and shorter construction durations. After construction, economic benefit will be found in reduced operating and maintenance costs, largely due to reduced operating and maintenance staffing requirements. Construction aspects

  16. The Korean Peninsula

    International Nuclear Information System (INIS)

    Jeon Bu-Guan

    1994-01-01

    A realistic approach to North-South arms control and disarmament would require a step-by-step formula encompassing measures for political and military confidence building, arms limitation and reduction. The most fundamental and important condition for achieving meaningful results in disarmament talks is securing political and military confidence. The problem which arose on the Korean peninsula originates from relations of North Korea and IAEA. North Korean position poses a serious threat to the Non-proliferation Treaty, in particular to the IAEA Safeguards regime. Nuclear non-proliferation and the ultimate elimination of nuclear weapons are the primary concerns of the post-cold war era. The Government of South Korea hopes that this issue can be solved through dialogue and negotiations

  17. Legal status of minister's notices and technology standards of 'Korea institute of nuclear safety'(KINS) to regulate nuclear safety

    International Nuclear Information System (INIS)

    Jung, S. K.; Jung, M. M.; Kim, S. W.; Jang, K. H.; Oh, B. J.

    2003-01-01

    Concerning nuclear safety or technology standards, each of 'notices' issued by minister of science and technology(MOST) empowered by law of its regulation is obviously forceful as a law, if not all. But the standards made by the chief of Korea institute of nuclear safety(KINS) to meet the tasks entrusted to KINS by MOST is only conditionally forceful as a law, that is, on the condition that law or regulation empowered the chief of KINS to make nuclear safety and/or technology standards

  18. American National Standards and the DOE - A cooperative effort to promote nuclear criticality safety

    International Nuclear Information System (INIS)

    Rothleder, B.M.

    1996-01-01

    The U.S. Department of Energy's (DOE's) new criticality safety order, DOE Order 420.1 (open-quotes Facility Safety,close quotes October 13, 1995), Sec. 4.3 (open-quotes Nuclear Criticality Safetyclose quotes), invokes, as an integral part, 12 appropriate American National Standards Institute/American Nuclear Society (ANSI/ANS) Series-8 standards for nuclear criticality safety, but with modifications. (The order that 420.1/4.3 replaced also invoked some ANSI/ANS Series-8 standards.) These modifications include DOE operation-specific exceptions to the standards and elaborations on some of the wording in the standards

  19. Environmental monitoring standardization of effluent from nuclear fuel cycle facilities in China

    International Nuclear Information System (INIS)

    Gao Mili

    1993-01-01

    China has established some environmental monitoring standards of effluent from nuclear fuel cycle facilities. Up to date 33 standards have been issued; 10 to be issued; 11 in drafting. These standards cover sampling, gross activities measurement, analytical methods and management rules and so on. They involve with almost all nuclear fuel cycle facilities and have formed a complete standards system. By the end of the century, we attempt to draft a series of analytical and determination standards in various environmental various medium, they include 36 radionuclides from nuclear fuel cycle facilities. (3 tabs.)

  20. Criteria, standards and policies regarding decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Detilleux, E.; Lennemann, W.

    1977-01-01

    The paper discusses the decontamination and decommissioning experiences encountered at the Eurochemic fuel reprocessing plant, their implications and the knowledge gained from these experiences. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The conlusions which are presented should weigh heavily in the considerations of the national authorities involved in regulating nuclear power programmes. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who jointly should make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities [fr

  1. 78 FR 37325 - License Renewal of Nuclear Power Plants; Generic Environmental Impact Statement and Standard...

    Science.gov (United States)

    2013-06-20

    ... Nuclear Power Plants; Generic Environmental Impact Statement and Standard Review Plans for Environmental... for Nuclear Power Plants, Supplement 1: Operating License Renewal'' (ESRP). The ESRP serves as a guide... published a final rule, ``Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating...

  2. Nuclear technology transfer via standards: the OMB Circular A-119 in action

    International Nuclear Information System (INIS)

    Zapp, F.C.

    1986-01-01

    The Performance Assurance Project Office (PAPO) has 23 nuclear energy (NE) standards in some phase of conversion to the national consensus standards, and identified three new NE standards for possible conversion. The author describes the methods of developing a consensus for standards through the use of working groups and ballots and the process of adopting a standard. Voluntary NE standards categories cover operation, instrumentation and controls, equipment, programs and procedures, materials, electrical, and structures and building. 4 references, 2 tables

  3. Criteria, standards and policies regarding decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Detilleux, E.; Lennemann, W.L.

    1977-01-01

    At the end of this century, there will probably be around 2500 operating nuclear power reactors, along with all the other nuclear fuel cycle facilities supporting their operation. Eventually these facilities, one by one, will be shut down and it will be necessary to dispose of them as with any redundant industrial facility or plant. Some parts of a nuclear fuel cycle facility can be dismantled by conventional methods, but those parts which have become contaminated with radioactive nuclear products or induced radioactivity must be subject to rigid controls and restrictions and handled by special dismantling and disposal procedures. In many cases, the resulting quantity of radioactive waste is likely to be relatively large and dismantling quite costly. Decommissioning nuclear facilities is a multifaceted problem involving planners, design engineers, operators, waste managers and regulatory authorities. Preparation for decommissioning should begin as early as site selection and plant design. The corner stone for the preparation of a decommissioning programme is the definition of its extent, meeting the requirements for public and environmental protection during the period that the radioactive material is of concern. The paper discusses the decontamination and decommissioning experience at the Eurochemic fuel reprocessing plant, the implications and the knowledge gained from this experience. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who should jointly make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities

  4. Analysis of the Current Technical Issues on ASME Code and Standard for Nuclear Mechanical Design(2009)

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Lee, B. S.; Yoo, S. H.

    2009-11-01

    This report describes the analysis on the current revision movement related to the mechanical design issues of the U.S ASME nuclear code and standard. ASME nuclear mechanical design in this report is composed of the nuclear material, primary system, secondary system and high temperature reactor. This report includes the countermeasures based on the ASME Code meeting for current issues of each major field. KAMC(ASME Mirror Committee) of this project is willing to reflect a standpoint of the domestic nuclear industry on ASME nuclear mechanical design and play a technical bridge role for the domestic nuclear industry in ASME Codes application

  5. Report on the Current Technical Issues on ASME Nuclear Code and Standard

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Lee, B. S.; Yoo, S. H.

    2008-11-01

    This report describes the analysis on the current revision movement related to the mechanical design issues of the U.S ASME nuclear code and standard. ASME nuclear mechanical design in this report is composed of the nuclear material, primary system, secondary system and high temperature reactor. This report includes the countermeasures based on the ASME Code meeting for current issues of each major field. KAMC(ASME Mirror Committee) of this project is willing to reflect a standpoint of the domestic nuclear industry on ASME nuclear mechanical design and play a technical bridge role for the domestic nuclear industry in ASME Codes application

  6. Analysis of the Current Technical Issues on ASME Code and Standard for Nuclear Mechanical Design(2009)

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Gyeong Hoi; Lee, B. S.; Yoo, S. H.

    2009-11-15

    This report describes the analysis on the current revision movement related to the mechanical design issues of the U.S ASME nuclear code and standard. ASME nuclear mechanical design in this report is composed of the nuclear material, primary system, secondary system and high temperature reactor. This report includes the countermeasures based on the ASME Code meeting for current issues of each major field. KAMC(ASME Mirror Committee) of this project is willing to reflect a standpoint of the domestic nuclear industry on ASME nuclear mechanical design and play a technical bridge role for the domestic nuclear industry in ASME Codes application

  7. Standard specification for nuclear-grade beryllium oxide powder

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    This specification defines the physical and chemical requirements of nuclear-grade beryllium oxide (BeO) powder to be used in fabricating nuclear components. This specification does not include requirements for health and safety. It recognizes the material as a Class B poison and suggests that producers and users become thoroughly familiar with and comply to applicable federal, state and local regulations and handling guidelines. Special tests and procedures are given

  8. Radiation protection standards in nuclear-fuel manufacturing

    International Nuclear Information System (INIS)

    Nilson, R.; Malody, C.W.

    1983-01-01

    The authors discuss principally the impact of changes in 10 CFR 20 on the commercial nuclear-fuel-fabrication industry, for which the impact appears to be the most severe, dwelling on the changes affecting occupational exposures. They conclude that the credibility of the nuclear industry as a comparably safe industry could be harmed by the continuing examination of apparent problem areas without establishing an overall perspective regarding employee safety. 21 references

  9. DOE [Department of Energy]-Nuclear Energy Standards Program annual assessment, FY 1990

    International Nuclear Information System (INIS)

    Williams, D.L. Jr.

    1990-11-01

    To meet the objectives of the programs funded by the Department of Energy (DOE)-Nuclear Energy (NE) Technology Support Programs, the Performance Assurance Project Office (PAPO) administers a nuclear standards program and related activities and fosters the development and application of standards. This standards program is carried out in accordance with the principles in DOE Order 1300.2, Department of Energy Standards Program, December 18, 1980. The purposes of this effort, as set forth in three subtasks, are to (1) manage the NE Standards Program, (2) manage the development and maintenance of NE standards, and (3) operate an NE Standards Information Program. This report assesses the Performance Assurance Project Office (PAPO) activities in terms of the objectives of the Department of Energy-Nuclear Energy (DOE-NE) funded programs. To meet these objectives, PAPO administers a nuclear standards program and related activities and fosters the development and application of standards. This task is carried out in accordance with the principles set forth in DOE Order 1300.2, Department of Energy Standards Program, December 18, 1980, and DOE memorandum, Implementation of DOE Orders on Quality Assurance, Standards, and Unusual Occurrence Reporting for Nuclear Energy Programs, March 3, 1982, and with guidance from the DOE-NE Technology Support Programs. 1 tab. (JF)

  10. An operational approach to standard nuclear process model (SNPM) and SAP nuclear software implementation at Slovenske Elektrarne

    International Nuclear Information System (INIS)

    Warren, C.C.

    2010-01-01

    Benchmarking efforts in the fall of 2006 showed significant performance gaps in multiple measured processes between the Slovenske Elektrarne (SE) nuclear organization and the highest performing nuclear organizations in the world. While overall performance of the SE nuclear fleet was good and in the second quartile, when compared to the worldwide population of Pressurized Water Reactors (PWR), SE leadership set new goals to improve safety and operational performance to the first decile of the worldwide PWR Fleet. To meet these goals the SE nuclear team initiated a project to identify and implement the Best Practice nuclear processes in multiple areas. The benchmarking process identified the Standard Nuclear Performance Model (SNPM), used in the US nuclear fleet, as the industry best practice process model. The Slovenske Elektrarne nuclear management team used various change management techniques to clearly establish the case for organizational and process change within the nuclear organization. The project organization established by the SE nuclear management team relied heavily on functional line organization personnel to gain early acceptance of the project goals and methods thereby reducing organizational opposition to the significant organizational and process changes. The choice of a standardized process model used, all or in part, by approximately one third of the nuclear industry worldwide greatly facilitated the development and acceptance of the changes. Use of a nuclear proven templated software platform significantly reduced development and testing efforts for the resulting fully integrated solution. In the spring of 2007 SE set in motion a set of initiatives that has resulted in a significant redesign of most processes related to nuclear plant maintenance and continuous improvement. Significant organizational structure changes have been designed and implemented to align the organization to the SNPM processes and programs. The completion of the initial

  11. An operational approach to standard nuclear process model (SNPM) and SAP nuclear software implementation at Slovenske Elektrarne

    Energy Technology Data Exchange (ETDEWEB)

    Warren, C.C. [Nuclear Power Plants Operation Department, Slovenske Elektrarne, a.s., Mlynske nivy 47, 821 09 Bratislava (Slovakia)

    2010-07-01

    Benchmarking efforts in the fall of 2006 showed significant performance gaps in multiple measured processes between the Slovenske Elektrarne (SE) nuclear organization and the highest performing nuclear organizations in the world. While overall performance of the SE nuclear fleet was good and in the second quartile, when compared to the worldwide population of Pressurized Water Reactors (PWR), SE leadership set new goals to improve safety and operational performance to the first decile of the worldwide PWR Fleet. To meet these goals the SE nuclear team initiated a project to identify and implement the Best Practice nuclear processes in multiple areas. The benchmarking process identified the Standard Nuclear Performance Model (SNPM), used in the US nuclear fleet, as the industry best practice process model. The Slovenske Elektrarne nuclear management team used various change management techniques to clearly establish the case for organizational and process change within the nuclear organization. The project organization established by the SE nuclear management team relied heavily on functional line organization personnel to gain early acceptance of the project goals and methods thereby reducing organizational opposition to the significant organizational and process changes. The choice of a standardized process model used, all or in part, by approximately one third of the nuclear industry worldwide greatly facilitated the development and acceptance of the changes. Use of a nuclear proven templated software platform significantly reduced development and testing efforts for the resulting fully integrated solution. In the spring of 2007 SE set in motion a set of initiatives that has resulted in a significant redesign of most processes related to nuclear plant maintenance and continuous improvement. Significant organizational structure changes have been designed and implemented to align the organization to the SNPM processes and programs. The completion of the initial

  12. A call for the adoption of nuclear utility information standards

    International Nuclear Information System (INIS)

    Slone, B.J. III; Richardson, C.E.

    1993-01-01

    In December 1986, the International Organization for Standardization (SO) issued a standard for document representation, ISO 8879, open-quotes Standard Generalized Markup Languageclose quotes (SGML). The standard prescribes a method for defining documents in two parts, one containing text and the other describing its structure without reference to word processing or publishing system software or hardware. It provides a method for open-quotes marking upclose quotes information, a way to place open-quotes tagsclose quotes on pieces of information to define their purpose. The SGML is part of a group of ISO standards titled open-quotes Information Processing-Text and Office Systems.close quotes This group contains the Document Style Specification and Semantics Language, the Standard Document Interchange Format, the Standard Page Description Language, and the fonts standard. The Department of Defense (DoD) has taken a standards initiative to improve the efficiency and reliability of systems by mandating that DoD suppliers comply with specific standards when delivering technical information. The initiative is called the Computer-aided Acquisition and Logistics Support (CALS) and includes a package of standards to address engineering drawings, raster font images, vector illustrations, text, and magnetic tape format. SGML is the CALS standard for documentation representation. Other industries have adopted this standard. Several industry groups, such as the Air Transport Association, American Association of Publishers, and the Telecommunications Industry Forum, are moving ahead vigorously with their own applications of SGML. The Institute of Electrical and Electronics Engineers has also adopted the ISO standard for production of its documents. Work is under way to develop their own SGML application

  13. History and Reality:the background and origin of the North Korean nuclear crisis%历史与现实:朝鲜核危机的背景和缘起

    Institute of Scientific and Technical Information of China (English)

    程晓勇

    2013-01-01

    After the cold war, the North Korea nuclear problem become the dominant problem between U.S. - North Korean relationship, and became the profoundest factor to the regional security in the Korean Peninsula and Northeast A-sia. North Korea nuclear crisis is caused by complex and profound historical and realistic background. After World War I-I, the Korean Peninsula was split into two parts, the North and the South. Korean War in the 1950s’ and “cold peace”between the South and the North in the past forty years are the main causes of nuclear crisis in North Korea. Superfi-cially, North Korean nuclear crisis is the result of “nuclear proliferation”. However, if we probe into this problem further, we may find that the core reason of the North Korean nuclear crisis is the Korea Peninsula security pattern changes in the relations between DPRK rigid contradictions after the cold war.%  朝鲜核危机是冷战后主导美朝关系,并深刻影响朝鲜半岛安全和东北亚地区稳定局势的最大因素。朝鲜核危机有着复杂而深刻的历史与现实背景,朝鲜半岛在二战后的南北分裂,上世纪50年代的朝鲜战争以及战后南北双方持续四十几年的“冷和平”状态,是朝核危机的深层次背景因素。表面上看,朝鲜核危机是由于“核扩散”而引发的,但是,透过朝核危机的表象,朝鲜核危机爆发的根本原因是冷战后朝鲜半岛安全格局发生的变化与朝美关系僵化不变的矛盾对立,是“此变”与“彼不变”对立冲突的结果。

  14. Study on the Correlation between PSR and Korean Stress Test for Continued Operation of Aging NPP

    International Nuclear Information System (INIS)

    Chung, June Ho; Kim, Tae Ryong

    2013-01-01

    Nuclear Safety and Security Commission (NSSC), Korean nuclear regulatory authority established the stress test guideline based on the EU stress test, and KHNP prepared the execution plan in response to the guideline for the CO of Kori Unit 1 and Wolsong Unit 1. PSR is a comprehensive safety review program for long term operation of NPP, which was developed by IAEA. Korea adopted PSR in 1999 as the regulatory requirement for CO of NPP. The IAEA standard guideline for PSR program was updated in 2003. However, the Korean PSR has not been revised yet to apply the new IAEA guidelines. Additionally, national legal systems and guidelines associated with the adoption of stress tests are urgently required as well. These revisions are imperative in order to ensure the reliability of NPPs, and to promote public acceptance and understanding. This study presents the technical basis and proposals for review actions necessary to address the issues and controversies surrounding the continued operation and decommissioning of aging NPPs in Korea. As discussed earlier in characteristics of Korean Stress Test, it is more comprehensive than the EU Stress Test in terms of its multilateral evaluation which includes equipment durability, plant operation, human factors, and safety margins, hence substantially raising the significance and value of the evaluation process. Thus, the addition of Korean Stress Test to the existing Korean Evaluation of CO is expected to greatly increase the quality of safety assessment of aging NPPs in Korea due to its stricter safety policies, hence providing a more meaningful evaluation process. However, a one-time application of the Korean Stress Test to only Kori Unit 1 and Wolsong Unit 1 would be a waste of the great effort that has been done thus far to improve the Korean Evaluation of CO and develop the Korean Stress Test. By extending the Korean Stress Test to all NPPs in Korea would maintain and ensure the reliability of NPPs as well as public

  15. Search for adequate quality standards for neutron radiography of nuclear fuel

    International Nuclear Information System (INIS)

    Domanus, J.C.

    1983-01-01

    Unlike in other fields of industrial radiography, where standard methods and procedures are used to control the quality of the radiographic image, no such standard exists for neutron radiography of nuclear fuel. To fill that gap it was felt that standardization work ought to be started in that field, too. Accordingly in 1979 an Euratom Neutron Radiography Working Group was constituted, which initiated standardization work in the field of neutron radiography of nuclear fuel. Finding adequate standards for image quality of neutron radiographs and checking the accuracy of dimension measurements from them were given first priority. (Auth.)

  16. Standard Specification for Nuclear Facility Transient Worker Records

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1995-01-01

    1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. 1.2 This specification applies to records to be used for in-processing only. 1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications). 1.4 This specification does not reduce any regulatory requirement for records retention at a licensed nuclear facility. Note 1—Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD...

  17. IEEE [Institute of Electrical and Electronics Engineers] standards and nuclear software quality engineering

    International Nuclear Information System (INIS)

    Daughtrey, T.

    1988-01-01

    Significant new nuclear-specific software standards have recently been adopted under the sponsorship of the American Nuclear Society and the American Society of Mechanical Engineers. The interest of the US Nuclear Regulatory Commission has also been expressed through their issuance of NUREG/CR-4640. These efforts all indicate a growing awareness of the need for thorough, referenceable expressions of the way to build in and evaluate quality in nuclear software. A broader professional perspective can be seen in the growing number of software engineering standards sponsored by the Institute of Electrical and Electronics Engineers (IEEE) Computer Society. This family of standards represents a systematic effort to capture professional consensus on quality practices throughout the software development life cycle. The only omission-the implementation phase-is treated by accepted American National Standards Institute or de facto standards for programming languages

  18. Nuclear Option in Korea

    International Nuclear Information System (INIS)

    Han, K. I.

    2002-01-01

    With sixteen(16) operating nuclear units in Korea, the share of nuclear power generation reached 41% of the total electric power generation as of December 2000. A prediction is that it would further increase to 44.5% by year 2015 according to the national long term power development plan. Four units are currently under construction with 6 more units in order. With little domestic energy resource and increasing energy demand to support national economic growth, Korea has chosen nuclear power as one of the major energy sources to ensure stable power supply and to promote energy self-sufficiency. It has been recognized that nuclear power in Korea is not a selective option but rather a necessity. The Korean nuclear power development started with construction of a 600 MWe size reactor that was designed and constructed by foreign vendors. As the national grid capacity became larger, the size of nuclear units increased to 1000 MWe class. In the mean time, the need for nuclear technology self-reliance grew not only in operation and maintenance but also in construction, manufacturing and design. For this, a nuclear technology self-reliance program has been embarked with the support of the Government and utility, and the 1000 MWe class KSNP(Korean Standard Nuclear Power Plant) has been developed. The KSNPs are currently being designed, manufactured, constructed and operated by relevant Korean entities themselves. To fit into a larger capacity national grid and also to improve nuclear economic competitiveness, the 1400 MWe class KNGR(Korean Next Generation Reactor) design has been developed uprating the 1000 MWe KSNP design. Its construction project is currently under contract negotiation, and is planned to be finished by 2010. In the mean time, to be ready for future electric power market deregulation, the 600 MWe class small KSNP design is being developed downsizing the KSNP. A modular small size reactor, SMART(System Integrated Modular Advanced Reactor) is also being

  19. States and tendencies of German standards in the field of nuclear filter technology

    International Nuclear Information System (INIS)

    Fichtner, N.; Sinhuber, D.

    1977-01-01

    The current situation in the Federal Republic of Germany with regard to standards and guidelines in the field of filter technology, as they apply to nuclear technology, is first presented. A detailed discussion follows of the results arrived at by the Nuclear Technology Standards Committee in its deliberations on the Standards' project DIN 25 414 'Ventilation equipment in nuclear power stations'. Particular attention is paid to the technical safety requirements for particulate filters, filter casings and filter housings, and methods of testing. The results so far obtained as regards filters in ventilation plant for pressurized water reactors are also dealt with

  20. National Construction of Global Education: A Critical Review of the National Curriculum Standards for South Korean Global High Schools

    Science.gov (United States)

    Sung, Youl-Kwan; Park, Minjeong; Choi, Il-Seon

    2013-01-01

    In this paper, the authors investigate what global visions of education are reflected in the selected national curriculum standards, with special reference to two seemingly contradictory forces: globalization and nationalism. This paper examines the socio-economic and cultural foundations of the curriculum and explains how the national curriculum…

  1. A complete analysis of a nuclear building to nuclear safety standards

    International Nuclear Information System (INIS)

    Bergeretto, G.; Giuliano, V.; Lazzeri, L.

    1975-01-01

    The nuclear standards impose on the designer the necessity of examining the loads, stresses and strains in a nuclear building even under extreme loading conditions, both due to plant malfunctions and environmental accidents. It is necessary then to generate, combine and examine a tremendous amount of data; really the lack of symmetry and general complication of the structures and the large number of loading combinations make an automatic analysis quite necessary. A largely automatized procedure is presented in view of solving the problem by a series of computer programs linked together as follows. After the seismic analysis has been performed by (SADE CODE) these data together with the data coming from thermal specifications, weight, accident descriptions etc. are fed into a finite element computer code (SAP4) for analysis. They are processed and combined by a computer code (COMBIN) according to the loading conditions (the usual list in Italy is given and briefly discussed), so that for each point (or each selected zone) under each loading condition the applied loads are listed. These data are fed to another computer code (DTP), which determines the amount of reinforcing bars necessary to accommodate the most severe of the loading conditions. The Aci 318/71 and Italian regulation procedures are followed; the characteristics of the program are briefly described and discussed. Some particular problems are discussed, e.g. the thermal stresses due to normal and accident conditions, the inelastic behavior of some frame elements (due to concrete cracking) is considered by means of an 'ad hoc' code. Typical examples are presented and the results are discussed showing a relatively large benefit in considering this inelastic effect

  2. Standardization of nuclear power plants in the United States: recent regulatory developments

    International Nuclear Information System (INIS)

    Cowan, B.Z.; Tourtellotte, J.R.

    1992-01-01

    On April 18, 1989, the United States (U.S.) Nuclear Regulatory Commission (NRC) amended the regulations governing the process for licensing nuclear power plants in the United States to provide for issuance of early site permits, standard design certifications and combined construction permits and operating licenses for nuclear power reactors. The new regulations are designed to achieve early resolution of licensing issues and facilitate standardization of nuclear power plants in the United States. The program for design standardization is central to efforts mounted by the U.S. government and industry to ensure that there will be a next generation of nuclear power facilities in the U.S. The most significant changes are provisions for certification of standard designs and for issuance prior to start of construction of combined licenses which incorporate a construction permit and an operating license with conditions. Such certifications and combined licenses must contain tests, inspections and analyses, and acceptance criteria, which are necessary and sufficient to provide reasonable assurance that the facility has been constructed and will operate in accordance with the combined license. A number of significant implementation issues have arisen. In addition a major court case brought by several anti-nuclear groups is pending, challenging NRC authority to issue combined licenses. It is the goal of the U.S. nuclear industry to have the first of the next generation of standardized nuclear power plants ordered, licensed, constructed and on-line by the year 2000. (author)

  3. Defining nuclear medical file formal based on DICOM standard

    International Nuclear Information System (INIS)

    He Bin; Jin Yongjie; Li Yulan

    2001-01-01

    With the wide application of computer technology in medical area, DICOM is becoming the standard of digital imaging and communication. The author discusses how to define medical imaging file formal based on DICOM standard. It also introduces the format of ANMIS system the authors defined the validity and integrality of this format

  4. ASME nuclear codes and standards: Scope of coverage and current initiatives

    International Nuclear Information System (INIS)

    Eisenberg, G. M.

    1995-01-01

    The objective of this paper is to address the broad scope of coverage of nuclear codes, standards and guides produced and administered by the American Society of Mechanical Engineers (ASME). Background information is provided regarding the evolution of the present activities. Details are provided on current initiatives intended to permit ASME to meet the needs of a changing nuclear industry on a worldwide scale. During the early years of commercial nuclear power, ASME produced a code for the construction of nuclear vessels used in the reactor coolant pressure boundary, containment and auxiliary systems. In response to industry growth, ASME Code coverage soon broadened to include rules for construction of other nuclear components, and inservice inspection of nuclear reactor coolant systems. In the years following this, the scope of ASME nuclear codes, standards and guides has been broadened significantly to include air cleaning activities for nuclear power reactors, operation and maintenance of nuclear power plants, quality assurance programs, cranes for nuclear facilities, qualification of mechanical equipment, and concrete reactor vessels and containments. ASME focuses on globalization of its codes, standards and guides by encouraging and promoting their use in the international community and by actively seeking participation of international members on its technical and supervisory committees and in accreditation activities. Details are provided on current international representation. Initiatives are underway to separate the technical requirements from administrative and enforcement requirements, to convert to hard metric units, to provide for non-U. S. materials, and to provide for translations into non-English languages. ASME activity as an accredited ISO 9000 registrar for suppliers of mechanical equipment is described. Rules are being developed for construction of containment systems for nuclear spent fuel and high-level waste transport packagings. Intensive

  5. Nuclear power project construction quality acceptance standards Implementation and discussion

    International Nuclear Information System (INIS)

    Lai Shifu

    2013-01-01

    Project quality construction acceptance is an important element of nuclear power project quality management. Based on characteristics of NPP construction and refer to national construction quality acceptance code and industry regulation, this paper introduces and discusses NPP construction quality acceptance regulation improvement and implementation under current situation. (authors)

  6. Research on the management and endorsement of nuclear safety standards in the United States and its revelation for China

    Science.gov (United States)

    Liu, Ting; Tian, Yu; Yang, Lili; Gao, Siyi; Song, Dahu

    2018-01-01

    This paper introduces the American standard system, the Nuclear Regulatory Commission (NRC)’s responsibility, NRC nuclear safety regulations and standards system, studies on NRC’s standards management and endorsement mode, analyzes the characteristics of NRC standards endorsement management, and points out its disadvantages. This paper draws revelation from the standard management and endorsement model of NRC and points suggestion to China’s nuclear and radiation safety standards management.The issue of the “Nuclear Safety Law”plays an important role in China’s nuclear and radiation safety supervision. Nuclear and radiation safety regulations and standards are strong grips on the implementation of “Nuclear Safety Law”. This paper refers on the experience of international advanced countriy, will effectively promote the improvement of the endorsed management of China’s nuclear and radiation safety standards.

  7. KWOC [Key-Word-Out-of-Context] index of nuclear energy standards

    International Nuclear Information System (INIS)

    Jennings, S.D.

    1990-05-01

    One major task of the Nuclear Standards Program funded by the Department of Energy (DOE)-Nuclear Energy (NE) Technology Support Programs is to promote and support the use of standards by providing line managers and standards coordinators with data that facilitates their ability to utilize standards requirements. To meet this task, the Performance Assurance Project Office (PAPO) administers a Performance Assurance Information Program. The task is carried out in accordance with the principle set forth in DOE Order 1300.2, ''Department of Energy Standards Program,'' December 18, 1980, and DOE memorandum, ''Implementation of DOE Orders on Quality Assurance, Standards, and Unusual Occurrence Reporting for Nuclear Energy Programs,'' March 3, 1982, and with guidance from the DOE-NE Technology Support Programs. The purpose of this information program is to collect, compile, and distribute program-related information, reports, and publications for the benefit of the DOE-NE program participants

  8. Changes in standardized mortality rates from thyroid cancer in Korea between 1985 and 2015: Analysis of Korean national data.

    Science.gov (United States)

    Choi, Yun Mi; Kim, Won Gu; Kwon, Hyemi; Jeon, Min Ji; Han, Minkyu; Kim, Tae Yong; Shong, Young Kee; Hong, Sang Mo; Hong, Eun-Gyoung; Kim, Won Bae

    2017-12-15

    The incidence of thyroid cancer has increased very rapidly in Korea; however, most previous studies suggested that the mortality rate for thyroid cancer remained stable. The objective of the current study was to evaluate recent changes in standardized thyroid cancer mortality using data from Statistics Korea. Population and mortality data from 1985 through 2015 were obtained from Statistics Korea. Age-standardized mortality rates (ASMRs) from thyroid cancer per 100,000 population were calculated based on the World Health Organization standard population. In Korea, the ASMRs from thyroid cancer increased from 0.17 (95% confidence interval [CI], 0.17-0.18) per 100,000 in 1985 to 0.85 (95% CI, 0.83-0.86) per 100,000 in 2004, which was the highest among all countries. Subsequently, the ASMRs continuously decreased to 0.42 (95% CI, 0.41-0.43) per 100,000 between 2004 and 2015. The estimated annual percent change (APC) from 1985 to 2004 was 7.94 (95% CI, 6.43-9.46), and the corresponding value from 2004 to 2015 was -4.10 (95% CI, -5.76 to -2.40). Changes in the ASMRs reflected similar patterns in men (1985-2003: APC, 8.51; 2003-2015: APC, -4.32) and women (1985-2004: APC, 7.62; 2004-2015: APC, -4.38) and were also observed in older patients (aged ≥ 55 years). Thyroid cancer mortality in Korea increased until 2004 and then continuously decreased until 2015. Increases in the early diagnosis of thyroid cancer, changes in exposure to risk factors, and standardization in diagnosis and treatment may be associated with the decrease in thyroid cancer mortality in Korea. Cancer 2017; 123:4808-14. © 2017 American Cancer Society. © 2017 American Cancer Society.

  9. 10 CFR Appendix N to Part 52 - Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FOR NUCLEAR POWER PLANTS Pt. 52, App. N Appendix N to Part 52—Standardization of Nuclear Power Plant...

  10. Standard Reference Development of nuclear material for Tensile and Hardness Test Properties

    International Nuclear Information System (INIS)

    Choo, Y. S.; Kim, D. S.; Yoo, B. O.; Ahn, S. B.; Baik, S. J.; Chun, Y. B.; Kim, K. H.; Hong, K. P.; Ryu, W. S.

    2007-12-01

    Standard reference is a official approved data such a coefficient of physics, approved material properties, and etc., which should be analyzed and evaluated by scientific method to acquire official approval for accuracy and credibility of measured data and information. So it could be used broadly and continuously by various fields of nation and society. It is classified to effective standard reference, verified standard reference, and certified standard reference. There are sixteen fields in designated standard references such a physical chemistry field, material field, metal field, and the others. The standard reference of neutron irradiated nuclear structural material is classified to metal field. This report summarized the whole processes about data collection, data production, data evaluation and the suggestion of details evaluation technical standard for tensile and hardness properties, which were achieved by carry out the project 'nuclear material standard reference development' as a result

  11. Standard Reference Development of nuclear material for Tensile and Hardness Test Properties

    Energy Technology Data Exchange (ETDEWEB)

    Choo, Y. S.; Kim, D. S.; Yoo, B. O.; Ahn, S. B.; Baik, S. J.; Chun, Y. B.; Kim, K. H.; Hong, K. P.; Ryu, W. S

    2007-12-15

    Standard reference is a official approved data such a coefficient of physics, approved material properties, and etc., which should be analyzed and evaluated by scientific method to acquire official approval for accuracy and credibility of measured data and information. So it could be used broadly and continuously by various fields of nation and society. It is classified to effective standard reference, verified standard reference, and certified standard reference. There are sixteen fields in designated standard references such a physical chemistry field, material field, metal field, and the others. The standard reference of neutron irradiated nuclear structural material is classified to metal field. This report summarized the whole processes about data collection, data production, data evaluation and the suggestion of details evaluation technical standard for tensile and hardness properties, which were achieved by carry out the project 'nuclear material standard reference development' as a result.

  12. Overview of the ANS [American Nuclear Society] mathematics and computation software standards

    International Nuclear Information System (INIS)

    Smetana, A.O.

    1991-01-01

    The Mathematics and Computations Division of the American Nuclear Society sponsors the ANS-10 Standards Subcommittee. This subcommittee, which is part of the ANS Standards Committee, currently maintains four ANSI/ANS software standards. These standards are: Recommended Programming Practices to Facilitate the Portability of Scientific Computer Programs, ANS-10.2; Guidelines for the Documentation of Computer Software, ANS-10.3; Guidelines for the Verification and Validation of Scientific and Engineering Computer Programs for the Nuclear Industry, ANS-10.4; and Guidelines for Accommodating User Needs in Computer Program Development, ANS-10.5. 5 refs

  13. Standardization, diversity, and learning: A model for the nuclear power industry

    International Nuclear Information System (INIS)

    David, P.A.; Rothwell, G.S.

    1992-11-01

    The lack of standardization, frequently mentioned as a burden borne by the U.S. nuclear industry, is discussed. A simple model of learning and standardization is presented. It is shown that when the effects of learning through diversity are strong, the present value of long-run costs can be minimized with either complete standardization or with complete experimentation where no two reactors are similar in the early stages of the industry. The conclusion discusses the relevance of these and other analytical results to the present U.S. nuclear industry regarding standardization policies. 8 refs

  14. Should evacuation standards be reviewed after a nuclear accident?

    International Nuclear Information System (INIS)

    Nifenecker, Herve

    2011-10-01

    The author comments the current practices of post-accident management of nuclear disasters. He outlines the peculiarities of nuclear evacuations with respect to other disasters. After referring to the use of life expectancy or of the reduction of life expectancy, for example for smokers, he suggests that irradiation could be expressed this way and then provide some intuitive information. He discusses the notion of linear no-threshold relationship which has been introduced by the ICRP after analysis of cancers noticed on survivors of Hiroshima and Nagasaki. He addresses the case of Fukushima, the issue of low doses applied to large populations. He discusses the limitations of the linear no-threshold relationship. He discusses possible improvements of evacuation procedures

  15. Standard guide for drying behavior of spent nuclear fuel

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    1.1 This guide is organized to discuss the three major components of significance in the drying behavior of spent nuclear fuel: evaluating the need for drying, drying spent nuclear fuel, and confirmation of adequate dryness. 1.1.1 The guide addresses drying methods and their limitations in drying spent nuclear fuels that have been in storage at water pools. The guide discusses sources and forms of water that remain in SNF, its container, or both, after the drying process and discusses the importance and potential effects they may have on fuel integrity, and container materials. The effects of residual water are discussed mechanistically as a function of the container thermal and radiological environment to provide guidance on situations that may require extraordinary drying methods, specialized handling, or other treatments. 1.1.2 The basic issue in drying is to determine how dry the SNF must be in order to prevent issues with fuel retrievability, container pressurization, or container corrosion. Adequate d...

  16. American National Standard administrative practices for nuclear criticality safety, ANSI/ANS-8.19

    International Nuclear Information System (INIS)

    Smith, D.R.; Carson, R.W.

    1991-01-01

    American National Standard Administrative Practices for Nuclear Criticality Safety, ANSI/ANS-8.19, provides guidance for the administration of an effective program to control the risk of nuclear criticality in operations with fissile material outside reactors. The several sections of the standard address the responsibilities of management, supervisory personnel, and the criticality safety staff, as well as requirements and suggestions for the content of operating procedures, process evaluations, material control procedures, and emergency procedures

  17. American National Standard: guidelines for evaluating site-related geotechnical parameters at nuclear power sites

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    This standard presents guidelines for evaluating site-related geotechnical parameters for nuclear power sites. Aspects considered include geology, ground water, foundation engineering, and earthwork engineering. These guidelines identify the basic geotechnical parameters to be considered in site evaluation, and in the design, construction, and performance of foundations and earthwork aspects for nuclear power plants. Also included are tabulations of typical field and laboratory investigative methods useful in identifying geotechnical parameters. Those areas where interrelationships with other standards may exist are indicated

  18. Assessment of the announced North Korean nuclear test using long-range atmospheric transport and dispersion modelling.

    Science.gov (United States)

    De Meutter, Pieter; Camps, Johan; Delcloo, Andy; Termonia, Piet

    2017-08-18

    On 6 January 2016, the Democratic People's Republic of Korea announced to have conducted its fourth nuclear test. Analysis of the corresponding seismic waves from the Punggye-ri nuclear test site showed indeed that an underground man-made explosion took place, although the nuclear origin of the explosion needs confirmation. Seven weeks after the announced nuclear test, radioactive xenon was observed in Japan by a noble gas measurement station of the International Monitoring System. In this paper, atmospheric transport modelling is used to show that the measured radioactive xenon is compatible with a delayed release from the Punggye-ri nuclear test site. An uncertainty quantification on the modelling results is given by using the ensemble method. The latter is important for policy makers and helps advance data fusion, where different nuclear Test-Ban-Treaty monitoring techniques are combined.

  19. Personnel involved in the development of nuclear standards in the United States, 1975

    International Nuclear Information System (INIS)

    Johnson, E.B.

    1976-05-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The Directory has four major sections: personnel, employers, committees, and a KWIC Index of committee titles. The Directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities

  20. Personnel involved in the development of nuclear standards in the United States, 1976

    International Nuclear Information System (INIS)

    Johnson, E.B.

    1977-03-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The directory has four major sections: personnel, employers, committees, and a KWIC index of committee titles. The directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities

  1. Evaluation of the safety of the operating nuclear power plants built to earlier standards

    International Nuclear Information System (INIS)

    Menteseoglu, S.

    2001-01-01

    The objective of this paper is to provide practical assistance on judging the safety of a nuclear power plant, on the basis of a comparison with current safety standards and operational practices. For nuclear power plants built to earlier standards for which there are questions about the adequacy of the maintenance of the plant design and operational practices, a safety review against current standards and practices can be considered a high priority. The objective of reviewing nuclear power plants built to earlier standards against current standards and practices is to determine whether there are any deviations which would have an impact on plant safety. The safety significance of the issues identified should be judged according to their implications for plant design and operation in terms of basic safety concepts such as defence in depth and safety culture. In addition, this paper provides assistance on the prioritization of corrective measures and their implementation so as to approach an acceptable level of safety

  2. Personnel involved in the development of nuclear standards in the United States, 1976

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, E.B. (ed.)

    1977-03-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The directory has four major sections: personnel, employers, committees, and a KWIC index of committee titles. The directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities.

  3. Personnel involved in the development of nuclear standards in the United States, 1975

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, E.B. (ed.)

    1976-05-01

    The development of voluntary nuclear standards in the United States is an active and necessary endeavor of the technical community concerned with the safe, orderly, and economic development of the nuclear potential. There are almost 8000 people presently involved either in writing voluntary standards and codes or in the management and processing roles necessary for their approval and promulgation. This document records the current participation of these people as member, chairman, or secretary of about 900 identified committees and projects. The standards projects are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. The Directory has four major sections: personnel, employers, committees, and a KWIC Index of committee titles. The Directory can be used to identify those nuclear standards projects currently active, to indicate the participation of employers, and to recognize the contributions of individuals to these often interdisciplinary activities.

  4. Standard specification for nuclear-grade aluminum oxide pellets

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2008-01-01

    1.1 This specification applies to pellets of aluminum oxide that may be ultimately used in a reactor core, for example, as filler or spacers within fuel, burnable poison, or control rods. In order to distinguish between the subject pellets and “burnable poison” pellets, it is established that the subject pellets are not intended to be used as neutron-absorbing material. 1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.

  5. Methods and Effects of Safety Enhancement in Korean PSR

    International Nuclear Information System (INIS)

    Kim, Young Gab; Park, Jong Woon

    2009-01-01

    Periodic Safety Review (PSR) is a comprehensive study on a nuclear power plant safety, taking into account aspects such as operational history, ageing, safety analyses and advances in code and standards since the time of construction. In Korea, PSRs have been performed for 20 units and have been effectively used to obtain an overall view of actual plant safety to determine reasonable and practical modifications that should be made in order to obtain a higher level of safety approaching that of modern plants. Among many safety enhancements achieved from Korean PSRs, new safety analyses are the important methods to confirm plant safety by increasing safety margin for specific safety issues. Methods and effects of safety enhancements applied in Korean PSRs are reviewed in this paper in light of new safety analyses to obtain additional safety margins

  6. Design of nuclear spectroscopy electronics based on the EUROsystem standard

    International Nuclear Information System (INIS)

    Pahor, J.

    1987-11-01

    The development of modular nuclear instruments in the EUROcard system has been continued by the design of a staircase generator; such an instrument is needed for accurate testing of spectroscopy amplifiers. The generator provides very precisely defined steps with the period between them varying from 8 to 50 microseconds, the output voltage continuously variable from 2 to 5 V, and attenuated ion steps between 1 and 100. Great care was taken that individual steps exhibit no overshot, thus providing a very clean signal to the input of a tested amplifier. The circuitry is kept simple, and it can be easily constructed in any electronics laboratory. Figs

  7. Recommendations to reduce hand exposure for standard nuclear medicine procedures

    International Nuclear Information System (INIS)

    Sans-Merce, M.; Ruiz, N.; Barth, I.; Carnicer, A.; Donadille, L.; Ferrari, P.; Fulop, M.; Ginjaume, M.; Gualdrini, G.; Krim, S.; Mariotti, F.; Ortega, X.; Rimpler, A.; Vanhavere, F.; Baechler, S.

    2011-01-01

    The optimization of the extremity dosimetry of medical staff in nuclear medicine was the aim of the Work Package 4 (WP4) of the ORAMED project, a Collaborative Project (2008–2011) supported by the European Commission within its 7th Framework Programme. Hand doses and dose distributions across the hands of medical staff working in nuclear medicine departments were evaluated through an extensive measurement program involving 32 hospitals in Europe and 139 monitored workers. The study included the most frequently used radionuclides, 99m Tc- and 18 F-labelled radiopharmaceuticals for diagnostic and 90 Y-labelled Zevalin ® and DOTATOC for therapy. Furthermore, Monte Carlo simulations were performed in different predefined scenarios to evaluate separately the efficacy of different radiation protection measures by comparing hand dose distributions according to various parameters. The present work gives recommendations based on results obtained with both measurements and simulations. This results in nine practical recommendations regarding the positioning of the dosemeters for an appropriate skin dose monitoring and the best protection means to reduce the personnel exposure.

  8. The Economic Value of Korean Nuclear Power Industry in the National Economy: An Input-Output Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Lee, M. K.; Kim, S. S.; Lee, J. H.; Kim, S. H. [Nuclear Policy Research Division, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    In 1978, Korea introduced the first nuclear power plant, Kori-1 unit, in parallel with the nation's industrialization policy. Thereafter, Korea has carried out a very ambitious nuclear power program and sustained a strong commitment to nuclear power development. Thus, nuclear is a prime energy source which presently meets about 30 percent of Korea's power demands. Also, Korea won a contract for APR-1400 NPPs to the UAE in 2009 which led to Korea as a significant exporter in the world nuclear market. Recently, the new government of Korea has been launching 'Creative Economy', from this perspective, the quantitative contributions of nuclear sector to the national economic growth are required to be estimated. This paper is to estimate quantitatively the economic values created by nuclear power industry in the framework of national economy. The total economic values created by nuclear power industry are estimated to be 63.6 trillion won for the study period.

  9. An application of the IAEA GCS-R-3 Standard in Nuclear Quality Management System

    Energy Technology Data Exchange (ETDEWEB)

    Kim, D. I.; Juhn, P. E. [TUEV SUED Korea, Seoul (Korea, Republic of); Kwon, M. J. [TUEV SUED KOCEN, Seoul (Korea, Republic of)

    2012-03-15

    IAEA GCS-R-3 Standard (2006) is intended to help nuclear community establishing a nuclear quality management system that integrates such 6 elements as safety, health, environment, security, quality and economics. In the present paper, the management principles of GCS-R-3 Standard are compared with those of ISO 9001 and ASME N/A-1 Codes and Standards. The paper also summarizes the worldwide survey on application of GS-R-3, which was conducted by the TUEV SUED Korea in 2011. The result concludes that the top priority should be given to safety upon which the management system must be based, in proper coordination with other 5 elements to enhance nuclear safety, in particular after Fukushima Dais-Ici nuclear power accidents on 11{sup th} March 2011 in Japan.

  10. Standardization of computer programs - basis of the Czechoslovak library of nuclear codes

    International Nuclear Information System (INIS)

    Gregor, M.

    1987-01-01

    A standardized form of computer code documentation has been established in the CSSR in the field of reactor safety. Structure and content of the documentation are described and codes already subject to this process are mentioned. The formation of a Czechoslovak nuclear code library and facilitated discussion of safety reports containing results of standardized codes are aimed at

  11. Experience with nuclear safety standards development in non-governmental international organizations

    International Nuclear Information System (INIS)

    Becker, K.

    1985-01-01

    Besides the IAEA as a 'governmental' organization dealing with basic safety recommendations addressed primarily to the national regulatory bodies in developing countries, two closely related non-governmental international standards organizations have gained extensive experience in the field of nuclear standardization. Over more than 25 years since their formation, both (a) the International Organization for Standardization's (ISO) Technical Committee 85 'Nuclear Energy', in particular in its Sub-Committee 3 'Reactor Technology and Safety' and (b) the International Electrotechnical Commission's (IEC) Technical Committee 45 'Nuclear Instrumentation' have published numerous standards. A brief review is given of these, draft standards, and other documents planned to become international standards. Many of them deal with rather specialized topics typical for 'industrial' standards such as standardized procedures, instruments, methods, materials, test methods, terminology, and signs and symbols, but others are directly related to more basic safety issues. In some areas such as quality assurance, seismic aspects of siting and terminology, there has been in the past occasional overlap in the activities of the NUSS programme, IEC and ISO. Letters of Understanding have since 1981 contributed to clarifying the borderlines and to avoiding redundant efforts. Also, some experiences and problems are described arising, for example, from the harmonization of different national safety philosophies and traditions into universally accepted international standards, and the transfer of international standards into national standards systems. Finally, based on a recent comprehensive compilation of some 3300 nuclear standards and standards projects, an attempt is made to present a cost/benefit analysis and an outlook on future developments. (author)

  12. IAEA nuclear data for applications: Cross section standards and the reference input parameter library (RIPL)

    International Nuclear Information System (INIS)

    Capote Noy, Roberto; Nichols, Alan L.; Pronyaev, Vladimir G.

    2003-01-01

    An integral part of the activities of the IAEA Nuclear Data Section involves the development of nuclear data for a wide range of user applications. When considering low-energy nuclear reactions induced by neutrons, photons and charged particles, a detailed knowledge is required of the production cross sections over a wide energy range, spectra of emitted particles and their angular distributions. Two highly relevant IAEA data development projects are considered in this paper. Neutron reaction cross-section standards represent the basic quantities needed in nuclear reaction cross-section measurements and evaluations. These standards and the covariance matrices of their uncertainties were previously evaluated and released in 1987. However, the derived uncertainties were subsequently considered to be unrealistic low due to the effect of the low uncertainties obtained in fitting the light element standards to the R-matrix model; as a result, evaluators were forced to scale up the uncertainties to 'expected values'. An IAEA Coordinated Research Project (CRP) entitled 'Improvement of the Standard Cross Sections for Light Elements' was initiated in 2002 to improve the evaluation methodology for the covariance matrix of uncertainty in the R-matrix model fits, and to produce R-matrix evaluations of the important light element standards. The scope of this CRP has been substantially extended to include the preparation of a full set of evaluated standard reactions and covariance matrices of their uncertainties. While almost all requests for nuclear data were originally addressed through measurement programmes, our theoretical understanding of nuclear phenomena has reached a reasonable degree of reliability and nuclear modeling has become standard practice in nuclear data evaluations (with measurements remaining crucial for data testing and benchmarking). Since nuclear model codes require a considerable amount of numerical input, the IAEA has instigated extensive efforts to

  13. Analysis of World Nuclear Market and Strategy of Korean NPP's Competitiveness Improvement for Exportation

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Jae Young; Jeong, Yong Hoon [KAIST, Daejeon (Korea, Republic of); Roh, Seungkook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Chang, Soon Heung [Handong Global University, Pohang (Korea, Republic of)

    2016-10-15

    China, India and USA (nuclear adopted countries) are planning tremendous number of NPPs to meet their increasing electricity demand and Saudi Arabia, Vietnam (nuclear adopting countries) are also planning to include nuclear power in their energy mix as a long-term plan. Korea has exported 4 units of APR1400 to the UAE in December, 2009. Korea became sixth NPP supplier country and our economic feasibility and safety features were started to evaluate worldwide. Nuclear industries became a new driver of Korea’s export and nuclear industries in Korea are now expecting another NPP export to Middle-eastern countries, including UAE and Saudi Arabia, based on the first-mover’s advantage at the UAE. In 2000s, five countries (Japan, USA, France, Russia and Korea), which are able to build NPP, focused on NPP export more than domestic construction. Global trend of world nuclear market changed rapidly, especially after NPP export to the UAE. By the global trend, hegemony of nuclear market migrated from supplier country to buyer country. Nuclear companies started cooperating rather than competing. Financing to developing countries become more important. In general, one of the considerable combinations is Korea-Japan-USA alliance. Korea is in charge of EPC, Japan supports financing and deficient technology (with USA partner), and Japan-USA handles fuel supply and back-end fuel cycle based on new agreed terms of ROK-US Nuclear Cooperation Agreement. This combination was judged to best way to collaborate with global companies. Paying attention to many delayed (or potentially delayed) constructions from Russia, intercepting the construction work will be available in case of contracted countries. Korea can emphasize the short construction time, high responsiveness and mild/equal diplomatic position to the target countries.

  14. Issues and relationships among software standards for nuclear safety applications. Version 2.0

    International Nuclear Information System (INIS)

    Scott, J.A.; Preckshot, G.G.; Lawrence, J.D.; Johnson, G.L.

    1996-01-01

    Lawrence Livermore National Laboratory is assisting the Nuclear Regulatory Commission with the development of draft regulatory guides for selected software engineering standards. This report describes the results of the initial task in this work. The selected software standards and a set of related software engineering standards were reviewed, and the resulting preliminary elements of the regulatory positions are identified in this report. The importance of a thorough understanding of the relationships among standards useful for developing safety-related software is emphasized. The relationship of this work to the update of the Standard Review Plan is also discussed

  15. Protective mechanism of Korean Red Ginseng in cisplatin-induced ototoxicity through attenuation of nuclear factor-κB and caspase-1 activation.

    Science.gov (United States)

    Kim, Su-Jin; Kwak, Hyun Jeong; Kim, Dae-Seung; Choi, Hyun-Myung; Sim, Jung-Eun; Kim, Sung-Hoon; Um, Jae-Young; Hong, Seung-Heon

    2015-07-01

    Cisplatin is an effective anti-cancer drug; however, one of its side effects is irreversible sensorineural hearing damage. Korean Red Ginseng (KRG) has been used clinically for the treatment of various diseases; however, the underlying mechanism of KRG treatment of ototoxicity has not been studied extensively. The present study aimed to further investigate the mechanism of KRG on cisplatin-induced toxicity in auditory HEI-OC1 cells in vitro, as well as in vivo. The pharmacological effects of KRG on cisplatin-induced changes in the hearing threshold of mice were determined, as well as the effect on the impairment of hair cell arrays. In addition, in order to elucidate the protective mechanisms of KRG, the regulatory effects of KRG on cisplatin-induced apoptosis-associated gene levels and nuclear factor-κB (NF-κB) activation were investigated in auditory cells. The results revealed that KRG prevented cisplatin-induced alterations in the hearing threshold of mice as well as the destruction of hair cell arrays in rat organ of Corti primary explants. In addition, KRG inhibited cisplatin-mediated cell toxicity, reactive oxygen species generation, interleukin-6 production, cytochrome c release and activation of caspases-3 in the HEI-OC1 auditory cell line. Furthermore, the results demonstrated that KRG inhibited the activation of NF-κB and caspase-1. In conclusion, these results provided a model for the pharmacological mechanism of KRG and provided evidence for potential therapies against ototoxicity.

  16. Numerical analysis and nuclear standard code application to thermal fatigue

    International Nuclear Information System (INIS)

    Merola, M.

    1992-01-01

    The present work describes the Joint Research Centre Ispra contribution to the IAEA benchmark exercise 'Lifetime Behaviour of the First Wall of Fusion Machines'. The results of the numerical analysis of the reference thermal fatigue experiment are presented. Then a discussion on the numerical analysis of thermal stress is tackled, pointing out its particular aspects in view of their influence on the stress field evaluation. As far as the design-allowable number of cycles are concerned the American nuclear code ASME and the French code RCC-MR are applied and the reasons for the different results obtained are investigated. As regards a realistic fatigue lifetime evaluation, the main problems to be solved are brought out. This work, is intended as a preliminary basis for a discussion focusing on the main characteristics of the thermal fatigue problem from both a numerical and a lifetime assessment point of view. In fact the present margin of discretion left to the analyst may cause undue discrepancies in the results obtained. A sensitivity analysis of the main parameters involved is desirable and more precise design procedures should be stated

  17. A systematic approach to the training in the nuclear power industry: The need for standard

    International Nuclear Information System (INIS)

    Wilkinson, J.D.

    1995-01-01

    The five elements of a open-quotes Systematic Approach to Trainingclose quotes (SAT) are analysis, design, development, implementation and evaluation. These elements are also present in the effective application of basic process control. The fundamental negative feedback process control loop is therefore an excellent model for a successful, systematic approach to training in the nuclear power industry. Just as standards are required in today's manufacturing and service industries, eg ISO 9000, so too are control standards needed in the training industry and in particular in the training of nuclear power plant staff. The International Atomic Energy Agency (IAEA) produced its TECDOC 525 on open-quotes Training to Establish and Maintain the Qualification and Competence of Nuclear Power Plant Operations Personnelclose quotes in 1989 and the American Nuclear Society published its open-quotes Selection, Qualification, and Training of Personnel for Nuclear Power Plants, an American National Standardclose quotes in 1993. It is important that community colleges, training vendors and organizations such as the Instrument Society of America (ISA), who may be supplying basic or prerequisite training to the nuclear power industry, become aware of these and other standards relating to training in the nuclear power industry

  18. Choosing a standard reactor: International competition and domestic politics in Chinese nuclear policy

    International Nuclear Information System (INIS)

    Ramana, M.V.; Saikawa, Eri

    2011-01-01

    China has ambitious plans to expand its nuclear power capacity. One of the policy goals that high-level policymakers have desired is to base the nuclear program on a standardized reactor design. However, this has not materialized so far. By examining its nuclear reactor choices for individual projects, we argue that China’s policymaking process has been greatly influenced by international competition and domestic politics. Multiple international nuclear vendors are intent upon maintaining their respective niches in the expanding Chinese reactor market, and they have used various forms of economic and political pressure to achieve their objectives. On the other hand, China’s policymaking process is fragmented and the shifting power balances among powerful domestic actors do not allow a fixed path to be followed. Further, because of the high costs and potential profits involved, nuclear reactor choices in China have been driven not just by technical considerations but also by foreign and trade policy objectives. All of these make it unlikely that China will standardize the reactor type it constructs in the near future. -- Highlights: ► China’s nuclear power policymaking has been fragmented and without central control. ► Multiple domestic actors have pursued independent agendas. ► International nuclear vendors have intensely competed for Chinese reactor contracts. ► Economic, political and foreign policy goals have driven reactor contract decisions. ► China is unlikely to construct only a standardized reactor design.

  19. Consensus standards utilized and implemented for nuclear criticality safety in Japan

    International Nuclear Information System (INIS)

    Nomura, Yasushi; Okuno, Hiroshi; Naito, Yoshitaka

    1996-01-01

    The fundamental framework for the criticality safety of nuclear fuel facilities regulations is, in many advanced countries, generally formulated so that technical standards or handbook data are utilized to support the licensing safety review and to implement its guidelines. In Japan also, adequacy of the safety design of nuclear fuel facilities is checked and reviewed on the basis of licensing safety review guides. These guides are, first, open-quotes The Basic Guides for Licensing Safety Review of Nuclear Fuel Facilities,close quotes and as its subsidiaries, open-quotes The Uranium Fuel Fabrication Facility Licensing Safety Review Guidesclose quotes and open-quotes The Reprocessing Facility Licensing Safety Review Guides.close quotes The open-quotes Nuclear Criticality Safety Handbook close-quote of Japan and the Technical Data Collection are published and utilized to supply related data and information for the licensing safety review, such as for the Rokkasho reprocessing plant. The well-established technical standards and data abroad such as those by the American Nuclear Society and the American National Standards Institute are also utilized to complement the standards in Japan. The basic principles of criticality safety control for nuclear fuel facilities in Japan are duly stipulated in the aforementioned basic guides as follows: 1. Guide 10: Criticality control for a single unit; 2. Guide 11: Criticality control for multiple units; 3. Guide 12: Consideration for a criticality accident

  20. Project on standards on good behaviour for the civilian nuclear industry

    International Nuclear Information System (INIS)

    Strohl, Pierre; Derche, Bernard

    1995-01-01

    Nuclear energy has provoked complex and sometimes heated debates involving politic, economic, scientific and moral issues, objective data alongside irrational feelings, short-term calculations as well as concerns touching on the far-reaching of humanity and the earth. These debates go beyond national borders as it is obvious that even though each country may hold divergent positions regarding the development of nuclear energy, their effects have an international scope, and, therefore, must be taken into account by all nations, even those who do not operate nuclear installations. Whatever conclusion may be drawn from these debates, decisions on nuclear energy are always taken by the political authorities, almost always at the highest level, be it national or international. These political decisions then become the body of legal standards, particularly the regulations which govern how nuclear energy is used. The main standards are for technical and scientific quality, applying to energy resource needs, to the reasons why the nuclear industry should be developed, to radioprotection and nuclear security, to protection of the environment, to radioactive waste management, to information and consulting to the public, to international cooperation, to non-proliferation of atomic weapons and to physical protection of nuclear materials. (author)

  1. Development of Korean EDMG

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yunjung; Jee, Moonhak; Kim, Inhwan; Park, Munhee [Nuclear Safety Technology Research Laboratory, Daejeon (Korea, Republic of); Kim, Moonoh [Atomic Creative Technology, Seoul (Korea, Republic of)

    2014-05-15

    Safety feature is also needed to more effectively cope with site-wide events affecting multiple units. In this study, the accident mitigation approaches in US are reviewed. The most effective ways to strengthen the defense-in-depth of nuclear power installations are presented as EDMG(Extensive Damage Mitigation Guideline) and FLEX against extreme hazards such as a beyond-design-basis external event (BDBEE) that took place at Fukushima. A combination of the US EDMG and FLEX is applied to develop Korean EDMG, which will be developed to have two different types of EDMGs : 'Site EDMG' to be used for effective technical support to activated TSCs and management of corporate emergency response resources in coordination with the EOF as necessary; and 'Plant-Specific EDMG (for Extreme Event)' to be used by the Technical Support Center (TSC) of a unit where a total loss of control has occurred or plant control cannot be established from the Control Room and Remote Shutdown Panel. The development of Korean EDMG is expected to further enhance mitigation and coping capabilities against site-wide extreme hazard in Korea where a relatively large number of units are assembled on each nuclear power plant site.

  2. 10 CFR Appendix N to Part 50 - Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FACILITIES Pt. 50, App.N Appendix N to Part 50—Standardization of Nuclear Power Plant Designs: Permits To...

  3. Contribution of the C.E.A. to standardization of nuclear plant equipments

    International Nuclear Information System (INIS)

    Dumax, P.; Seran, R.

    1980-01-01

    In research and production laboratories working in the nuclear field standardization of equipments greatly improves the profits of the installation and the protection of individuals and goods. The standardization effort on technical equipments of shielding, handling, detection and safety (so called P.M.D.S.) initiated by the C.E.A. in 1967 is being carried out now within the Institute of Protection and Nuclear Safety (I.P.S.N.) by a technical Service specialized in protection and dosimetry (S.T.E.P.D.). Its purpose is to establish standardization documents for internal use and to take part in the work of official standardization organizations. The benefits of standardization are reviewed. The achievements of the various working groups common to C.E.A. centers are stated and the documents published or to be published are listed [fr

  4. Revision of AESJ standard 'the code of implemnetation of periodic safety review of nuclear power plants'

    International Nuclear Information System (INIS)

    Hirano, Masashi; Narumiya, Yoshiyuki

    2010-01-01

    The Periodic Safety Review (PSR) was launched in June 1992, when the Agency for Natural Resources and Energy issued a notification that required licensees to conduct comprehensive review on the safety of each existing nuclear power plant (NPP) once approximately every ten years based on the latest technical findings for the purpose of improving the safety of the NPP. In 2006, the Standard Committee of the Atomic Energy Society of Japan established the first version of 'The Standard of Implementation for Periodic Safety Review of Nuclear Power Plants: 2006'. Taking into account developments in safety regulation of PSR after the issuance of the first version, the Standard Committee has revised the Standard. This paper summarizes background on PSR, such developments are major contents of the Standard as well as the focal points of the revision. (author)

  5. A brief review of nuclear electronics standards . . . Past, present and future

    International Nuclear Information System (INIS)

    Larsen, R.S.

    2000-01-01

    Modular Nuclear Instrument Standards have played a key role in U. S. Department of Energy National Laboratories and similar scientific laboratories worldwide for more than three decades. The scientific and engineering efficiency and economic benefits have been well documented. Standards are constantly evolving with the introduction of new technologies and the present is a time of rapid change. This report is based on an invited talk presented at the Joint Meeting of the U.S. Nuclear Instrument Module (NIM) and European Standards for Norms in Electronics (ESONE) Standards Committees, Lyon, France, October 20, 2000. It provides a brief overview of past developments and attempts to identify areas of possible opportunities for renewed standardization efforts to meet future challenges

  6. Recent developments in the IAEA safety standards: design and operation of nuclear power plants

    International Nuclear Information System (INIS)

    Saito, Takehiko

    2004-01-01

    The IAEA has been publishing a wide variety of safety standards for nuclear and radiation related facilities and activities since 1978. In 1996, a more rigorously structured approach for the preparation and review of its safety standards was introduced. Currently, based on the approach, revision of most of the standards is in completion or near completion. The latest versions of the Safety Requirements for ''Design'' and ''Operation'' of nuclear power plants were respectively published in 2000. Currently, along with this revision of the Safety Requirements, many Safety Guides have been revised. In order to clarify the complicated revision procedure, an example of the entire revision process for a Safety Guide is provided. Through actual example of the revision process, enormous amount of work involved in the revision work is clearly indicated. The current status of all of the Safety Standards for Design and that for Operation of nuclear power plants are summarized. Summary of other IAEA safety standards currently revised and available related IAEA publications, together with information on the IAEA Web Site from where these documents can be downloaded, is also provided. The standards are reviewed to determine whether revision (or new issue) is necessary in five years following publication. The IAEA safety standards will continue to be updated through comprehensive and structured approach, collaboration of many experts of the world, and reflecting good practices of the world. The IAEA safety standards will serve to provide high level of safety assurance. (author)

  7. Development of a standard equipment management model for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Hee Seung; Ju, Tae Young; Kim, Jung Wun [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2012-10-15

    Most utilities that have achieved high performance have introduced a management model to improve performance and operate plants safely. The Nuclear Energy Institute has developed and updated its Standard Nuclear Performance Model (SNPM) in order to provide a summary of nuclear processes, cost definitions, and key business performance measures for business performance comparison and benchmarking. Over the past decade, Korea Hydro and Nuclear Power Co. (KHNP) has introduced and implemented many engineering processes such as Equipment Reliability (ER), Maintenance Rule (MR), Single Point Vulnerability (SPV), Corrective Action Program (CAP), and Self Assessment (SA) to improve plant performance and to sustain high performance. Some processes, however, are not well interfaced with other processes, because they were developed separately and were focused on the process itself. KHNP is developing a Standard Equipment Management Model (SEMM) to integrate these engineering processes and to improve the interrelation among the processes. In this paper, a draft model and attributes of the SEMM are discussed.

  8. Characterization of a metallic mechanical standard junction for a specific nuclear application

    International Nuclear Information System (INIS)

    Villanueva, Jose; Miller, Marcelo E.; Vazquez, Luis; Halpert, Silvia

    2007-01-01

    A testing procedure, targeted to promote that an industrial standard component can be used in a nuclear particular application, is designed and applied. Namely, a mechanical standard junction component, that is widely recognized for its industrial reliability, is commonly used to fit two stainless steel tubes, is intended to be used in a particular nuclear application fitting a stainless steel tube to a Zircaloy-4 tube counterpart. The junction will be subjected to pressure and temperature typical of primary circuit coolant in a nuclear power plant. The results found once the test was applied (catastrophic fault and significant water leakage absence) allow to advice using this mechanical junction device as a valid nuclear design option fitting the proposed tubes. (author) [es

  9. Development of a standard equipment management model for nuclear power plants

    International Nuclear Information System (INIS)

    Chang, Hee Seung; Ju, Tae Young; Kim, Jung Wun

    2012-01-01

    Most utilities that have achieved high performance have introduced a management model to improve performance and operate plants safely. The Nuclear Energy Institute has developed and updated its Standard Nuclear Performance Model (SNPM) in order to provide a summary of nuclear processes, cost definitions, and key business performance measures for business performance comparison and benchmarking. Over the past decade, Korea Hydro and Nuclear Power Co. (KHNP) has introduced and implemented many engineering processes such as Equipment Reliability (ER), Maintenance Rule (MR), Single Point Vulnerability (SPV), Corrective Action Program (CAP), and Self Assessment (SA) to improve plant performance and to sustain high performance. Some processes, however, are not well interfaced with other processes, because they were developed separately and were focused on the process itself. KHNP is developing a Standard Equipment Management Model (SEMM) to integrate these engineering processes and to improve the interrelation among the processes. In this paper, a draft model and attributes of the SEMM are discussed

  10. The impact of safety standards updating for design purposes in nuclear power plants licensing

    International Nuclear Information System (INIS)

    Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz

    2009-01-01

    The Brazilian experience of nuclear power plants licensing was consolidated by the use of the Brazilian, American, German and IAEA standards. Independently of the set of norms, standards or guides to be used, this set should be in consonance with the state-of-art or the current state of knowledge in science and technology. In the general design criteria of US NRC or German BMI, or in the Brazilian norms (CNEN) or even, in the IAEA standards, this aspect is always emphasized. On the other hand, the international operational experience of nuclear reactors (for example, TMI accident) also contributes to the updating of norms and standards. The use of new technologies (for example, digital technology) impels the norms and standards to adopt new design criteria related to the new technological context. Moreover, we must add the particular vision that each country can have concerning to specific topics in nuclear safety. This work discusses how the norms, standards and guides used in the nuclear licensing are being reviewed to cope with the requirement of the state-of-art. In order to accomplish this aim we took some general design criteria to exemplify how they are fulfilled, mainly those related directly with the protection of the defense-in-depth barriers: primary coolant system, containment vessel and containment systems, including external events and severe accidents. In complement to the deterministic analysis, it is also discussed the design criteria related to the human factors engineering and probabilistic safety analysis, including severe accidents aspects. (author)

  11. Method of using a nuclear magnetic resonance spectroscopy standard

    Science.gov (United States)

    Spicer, Leonard D.; Bennett, Dennis W.; Davis, Jon F.

    1985-01-01

    (CH.sub.3).sub.3 SiNSO is produced by the reaction of ((CH.sub.3).sub.3 Si).sub.2 NH with SO.sub.2. Also produced in the reaction are ((CH.sub.3).sub.3 Si).sub.2 O and a new solid compound [NH.sub.4 ][(CH.sub.3).sub.3 SiOSO.sub.2 ]. Both (CH.sub.3).sub.3 SiNSO and [NH.sub.4 ][(CH.sub.3).sub.3 SiOSO.sub.2 ] have fluorescent properties. The reaction of the subject invention is used in a method of measuring the concentration of SO.sub.2 pollutants in gases. By the method, a sample of gas is bubbled through a solution of ((CH.sub.3).sub.3 Si).sub.2 NH, whereby any SO.sub.2 present in the gas will react to produce the two fluorescent products. The measured fluorescence of these products can then be used to calculate the concentration of SO.sub.2 in the original gas sample. The solid product [NH.sub.4 ][(CH.sub.3).sub.3 SiOSO.sub.2 ] may be used as a standard in solid state NMR spectroscopy, wherein the resonance peaks of either .sup.1 H, .sup.13 C, .sup.15 N, or .sup.29 Si may be used as a reference.

  12. Evaluation of regulatory processes affecting nuclear power plant early site approval and standardization

    International Nuclear Information System (INIS)

    1983-12-01

    This report presents the results of a survey and evaluation of existing federal, state and local regulatory considerations affecting siting approval of power plants in the United States. Those factors that may impede early site approval of nuclear power plants are identified, and findings related to the removal of these impediments and the general improvement of the approval process are presented. A brief evaluation of standardization of nuclear plant design is also presented

  13. Reliability programs for nuclear power plants. Regulatory standard S-98 revision 1

    International Nuclear Information System (INIS)

    2005-07-01

    The purpose of this regulatory standard is to help assure, in accordance with the purpose of the Nuclear Safety and Control Act (NSCA), that a licensee who constructs or operates a nuclear power plant (NPP) develops and implements a reliability program that assures that the systems important to safety at the plant can and will meet their defined design and performance specifications at acceptable levels of reliability throughout the lifetime of the facility. This regulatory standard describes the requirements of a reliability program for a nuclear power plant. The licensee shall implement the requirements described in this regulatory standard when a condition of a licence or other legally enforceable instrument so requires.(author)

  14. Standard concerning the design of nuclear power stations in earthquake-prone districts

    International Nuclear Information System (INIS)

    Kirillov, A.P.; Anbriashivili, Y.K.; Suvilova, A.V.

    1980-01-01

    The measures of security assurance against the effect of radioactive contamination has become more and more complex due to the construction of nuclear power stations of diverse types. The aseismatic measures for the nuclear power stations built in the districts where earthquakes of different intensity occur are important problems. All main machinery and equipments and emergency systems in power stations must be protected from earthquakes, and this makes the solution of problems difficult. At present in USSR, the provisional standard concerning the design of atomic energy facilities built in earthquake-prone districts is completed. The basic philosophy of the standard is to decide the general requirements as the conditions for the design of nuclear power stations built in earthquake-prone districts. The lowest earthquake activity in the construction districts is considered as magnitude 4, and in the districts where earthquake activity is magnitude 9 or more, the construction of nuclear power stations is prohibited. Two levels of earthquake action are specified for the design: design earthquake and the largest design earthquake. The construction sites of nuclear power stations must be 15 to 150 km distant from the potential sources of earthquakes. Nuclear power stations are regarded as the aseismatically guaranteed type when the safety of reactors is secured under the application of the standard. The buildings and installations are classified into three classes regarding the aseismatic properties. (Kako, I.)

  15. Nuclear reactor pressure vessel surveillance capsule examinations. Application of American Society for Testing and Materials Standards

    International Nuclear Information System (INIS)

    Perrin, J.S.

    1978-01-01

    A series of pressure vessel surveillance capsules is installed in each commercial nuclear power plant in the United States. A capsule typically contains neutron dose meters, thermal monitors, tensile specimens, and Charpy V-notch impact specimens. In order to determine property changes of the pressure vessel resulting from irradiation, surveillance capsules are periodically removed during the life of a reactor and examined. There are numerous standards, regulations, and codes governing US pressure vessel surveillance capsule programmes. These are put out by the US Nuclear Regulatory Commission, the Boiler and Pressure Vessel Committee of the American Society of Mechanical Engineers, and the American Society for Testing and Materials (ASTM). A majority of the pertinent ASTM standards are under the jurisdiction of ASTM Committee E-10 on Nuclear Applications and Measurements of Radiation Effects. The standards, regulations, and codes pertaining to pressure vessel surveillance play an important role in ensuring reliability of the nuclear pressure vessels. ASTM E 185-73 is the Standard Recommended Practice for Surveillance Tests for Nuclear Reactors. This standard recommends procedures for both the irradiation and subsequent testing of surveillance capsules. ASTM E 185-73 references many additional specialized ASTM standards to be followed in specific areas of a surveillance capsule examination. A key element of surveillance capsule programmes is the Charpy V-notch impact test, used to define curves of fracture behaviour over a range of temperatures. The data from these tests are used to define the adjusted reference temperature used in determining pressure-temperature operating curves for a nuclear power plant. (author)

  16. Calculation of risk-based detection limits for radionuclides in the liquid effluents from Korean nuclear power plants

    International Nuclear Information System (INIS)

    Cheong, Jae Hak

    2017-01-01

    In order to review if present detection limits of radionuclides in liquid effluent from nuclear power plants are effective enough to warrant compliance with regulatory discharge limits, a risk-based approach is developed to derive a new detection limit for each radionuclide based on radiological criteria. Equations and adjustment factors are also proposed to discriminate the validity of the detection limits for multiple radionuclides in the liquid effluent with or without consideration of the nuclide composition. From case studies to three nuclear power plants in Korea with actual operation data from 2006 to 2015, the present detection limits have turned out to be effective for Hanul Unit 1 but may not be sensitive enough for Kori Unit 1 (8 out of 14 radionuclides) and Wolsong Unit 1 (9 out of 42 radionuclides). However, it is shown that the present detection limits for the latter two nuclear power plants can be justified, if credit is given to the radionuclide composition. Otherwise, consideration should be given to adjustment of the present detection limits. The risk-based approach of this study can be used to determine the validity of established detection limits of a specific nuclear power plant. (author)

  17. The north-Korean nuclear program. Round table. What do we know? What do we think we know? And what are the resulting actions?; Le programme nucleaire nord-coreen. Table ronde. Que savons-nous? Que croyons-nous savoir? Et quelles actions en resultent?

    Energy Technology Data Exchange (ETDEWEB)

    Pollack, J. [US Naval War College, Dept. des Recherches Strategiques, Newport (United States)

    2004-06-15

    The North-Korean nuclear program is problematic because of the specific government policy from which information are coming with difficulty. From open sources, the author takes stock on our knowledge concerning the military nuclear program of Pyongyang by looking on the two possible channels of nuclear matter production for nuclear weapons and on the weapons construction. He concludes on the actions to realize facing the uncertainties. (A.L.B.)

  18. The Canadian approach to nuclear codes and standards. A CSA forum for development of standards for CANDU: radioactive waste management and decommissioning

    International Nuclear Information System (INIS)

    Shin, T.; Azeez, S.; Dua, S.

    2006-01-01

    Together with the Canadian Standards Association (CSA), industry stakeholders, governments, and the public have developed a suite of standards for CANDU nuclear power plants that generate electricity in Canada and abroad. In this paper, we will describe: CSA's role in national and international nuclear standards development; the key issues and priority projects that the nuclear standards program has addressed; the new CSA nuclear committees and projects being established, particularly those related to waste management and decommissioning; the hierarchy of nuclear regulations, nuclear, and other standards in Canada, and how they are applied by AECL; the standards management activities; and the future trends and challenges for CSA and the nuclear community. CSA is an accredited Standards Development Organization (SDO) and part of the international standards system. CSA's Nuclear Strategic Steering Committee (NSSC) provides leadership, direction, and support for a standards committee hierarchy comprised of members from a balanced matrix of interests. The NSSC strategically focuses on industry challenges; a new nuclear regulatory system, deregulated energy markets, and industry restructuring. As the first phase of priority projects is nearing completion, the next phase of priorities is being identified. These priorities address radioactive waste management, environmental radiation management, decommissioning, structural, and seismic issues. As the CSA committees get established in the coming year, members and input will be solicited for the technical committees, subcommittees, and task forces for the following related subjects: Radioactive Waste Management; a) Dry Storage of Irradiated Fuel; b) Short-Term Radioactive Waste Management; c) Long-Term Storage and Disposal of Radioactive Waste. 2. Decommissioning Nuclear Power is highly regulated, and public scrutiny has focused Codes and Standards on public and worker safety. Licensing and regulation serves to control

  19. Integrating industry nuclear codes and standards into United States Department of Energy facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jacox, J.

    1995-02-01

    Recently the United States Department of Energy (DOE) has mandated facilities under their jurisdiction use various industry Codes and Standards developed for civilian power reactors that operate under U.S. Nuclear Regulatory Commission License. While this is a major step forward in putting all our nuclear facilities under common technical standards there are always problems associated with implementing such advances. This paper will discuss some of the advantages and problems experienced to date. These include the universal challenge of educating new users of any technical documents, repeating errors made by the NRC licensed facilities over the years and some unique problems specific to DOE facilities.

  20. Suggestions and comments about preliminary plans of ABNT 20:04.002-001 standard 'Seismic actions for nuclear facilities project'

    International Nuclear Information System (INIS)

    Soares, W.A.

    1984-01-01

    This paper presents an analysis of preliminary plans of standard 'seismic actions for nuclear facilities project'. This document presents since seismic event characterization up to details of structural project of nuclear facilities construction. (C.M.)

  1. Nuclear reactors' construction costs: The role of lead-time, standardization and technological progress

    International Nuclear Information System (INIS)

    Berthélemy, Michel; Escobar Rangel, Lina

    2015-01-01

    This paper provides an econometric analysis of nuclear reactor construction costs in France and the United States based on overnight costs data. We build a simultaneous system of equations for overnight costs and construction time (lead-time) to control for endogeneity, using change in expected electricity demand as instrument. We argue that the construction of nuclear reactors can benefit from standardization gains through two channels. First, short term coordination benefits can arise when the diversity of nuclear reactors' designs under construction is low. Second, long term benefits can occur due to learning spillovers from past constructions of similar reactors. We find that construction costs benefit directly from learning spillovers but that these spillovers are only significant for nuclear models built by the same Architect–Engineer. In addition, we show that the standardization of nuclear reactors under construction has an indirect and positive effect on construction costs through a reduction in lead-time, the latter being one of the main drivers of construction costs. Conversely, we also explore the possibility of learning by searching and find that, contrary to other energy technologies, innovation leads to construction costs increases. -- Highlights: •This paper analyses the determinants of nuclear reactors construction costs and lead-time. •We study short term (coordination gains) and long term (learning by doing) benefits of standardization in France and the US. •Results show that standardization of nuclear programs is a key factor for reducing construction costs. •We also suggest that technological progress has contributed to construction costs escalation

  2. Round table discussion: Quality control and standardization of nuclear medicine software

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    In summary the round table came to the following important conclusions: Nuclear medicine software systems need better documentation, especially regarding details of algorithms and limitations, and user friendliness could be considerably improved. Quality control of software is an integral part of quality assurance in nuclear medicine and should be performed at all levels of the software. Quality control of applications software should preferably be performed with assistance of generally accepted software phantoms. A basic form of standardization was welcomed and partly regarded as essential by all participants. Some areas such as patient study files could be standardized in the near future, whereas other areas such as the standardization of clinical applications programs or acquisition protocols still present major difficulties. An international cooperation in the field of standardization of software and other topics has already been started on the European level and should be continued and supported. (orig.)

  3. Catalogue and classification of technical safety standards, rules and regulations for nuclear power reactors and nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Fichtner, N.; Becker, K.; Bashir, M.

    1977-01-01

    The present report is an up-dated version of the report 'Catalogue and Classification of Technical Safety Rules for Light-water Reactors and Reprocessing Plants' edited under code No EUR 5362e, August 1975. Like the first version of the report, it constitutes a catalogue and classification of standards, rules and regulations on land-based nuclear power reactors and fuel cycle facilities. The reasons for the classification system used are given and discussed

  4. IEEE Standard for qualification of Class 1E lead storage batteries for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    This document describes qualification methods for Class 1E lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1979 and IEEE Std 308-1978, can be demonstrated by using the procedures provided in this Standard in accordance with IEEE Std 323-1974. Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other types batteries are beyond the scope of this Standard

  5. IEEE standard for qualification of class 1E lead storage batteries for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    IEEE Std 323-1974, Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, was developed to provide guidance for demonstrating and documenting the adequacy of electrical equipment used in all Class 1E and interface systems. This standard, IEEE Std 535-1979, was developed to provide specific methods and type test procedures for lead storage batteries in reference to IEEE Std 323-1974

  6. Selected review of regulatory standards and licensing issues for nuclear power plants

    International Nuclear Information System (INIS)

    Stevenson, J.D.; Thomas, F.A.

    1982-11-01

    This report presents a compilation and description of current foreign regulatory standards and licensing issues in the areas of interest associated with Siting, Structural Engineering, Metallurgy and Materials, and Mechanical Engineering. In addition, summary comparisons of the requirements of both the US and foreign nuclear power plant regulatory standards are provided. The selected foreign countries surveyed include Canada, France, Japan, Sweden, United Kingdom of Great Britain and Northern Ireland, and the Federal Republic of Germany

  7. IEEE standard for qualifying class IE equipment for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1974-01-01

    The Institute of Electrical and Electrical Engineers, Inc. (IEEE) standards for electrical equipment (Class IE) for nuclear power generating stations are given. The standards are to provide guidance for demonstrating and documenting the adequacy of electric equipment used in all Class IE and interface systems. Representative in containment design basis event conditions for the principal reactor types are included in the appendixes for guidance in enviromental simulation

  8. Methodology to evaluate the site standard seismic motion for a nuclear facility

    International Nuclear Information System (INIS)

    Soares, W.A.

    1983-03-01

    An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic priciples of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; avalable methodologies and recommended procedures to evaluate the site standard seismic motion. (E.G.) [pt

  9. A study on the application of two-dosimeter algorithm to estimate the effective dose in an inhomogeneous radiation field at Korean Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kim, Hee Geun; Kong, Tae Young

    2008-01-01

    In Korean Nuclear Power Plants (NPPs), two ThermoLuminescent Dosimeters (TLD) were provided to workers who work in an inhomogeneous radiation field; one on the chest and the other on the head. In this way, the effective dose for radiation workers at NPPs was determined by the high deep dose between two radiation dose from these TLDs. This represented a conservative method of evaluating the degree of exposure to radiation. In this study, to prevent the overestimation of the effective dose, field application experiments were implemented using two-dosimeter algorithms developed by several international institutes for the selection of an optimal algorithm. The algorithms used by the Canadian Ontario Power Generation (OPG) and American ANSI HPS N13.41, NCRP (55/50), NCRP (70/30), EPRI (NRC), Lakshmanan, and Kim (Texas A and M University) were extensively analyzed as two-dosimeter algorithms. In particular, three additional TLDs were provided to radiation workers who wore them on the head, chest, and back during maintenance periods, and the measured value were analyzed. The results found no significant differences among the calculated effective doses, apart from Lakshmanan's algorithm. Thus, this paper recommends the NCRP(55/50) algorithm as an optimal two-dosimeter algorithm in consideration of the solid technical background of NCRP and the convenience of radiation works. In addition, it was determined that a two-dosimeter is provided to a single task which is expected to produce a dose rate of more than 1 mSv/hr, a difference of dose rates depending on specific parts of the body of more than 30%, and an exposure dose of more than 2 mSv

  10. Development of a consensus standard for verification and validation of nuclear system thermal-fluids software

    International Nuclear Information System (INIS)

    Harvego, Edwin A.; Schultz, Richard R.; Crane, Ryan L.

    2011-01-01

    With the resurgence of nuclear power and increased interest in advanced nuclear reactors as an option to supply abundant energy without the associated greenhouse gas emissions of the more conventional fossil fuel energy sources, there is a need to establish internationally recognized standards for the verification and validation (V and V) of software used to calculate the thermal–hydraulic behavior of advanced reactor designs for both normal operation and hypothetical accident conditions. To address this need, ASME (American Society of Mechanical Engineers) Standards and Certification has established the V and V 30 Committee, under the jurisdiction of the V and V Standards Committee, to develop a consensus standard for verification and validation of software used for design and analysis of advanced reactor systems. The initial focus of this committee will be on the V and V of system analysis and computational fluid dynamics (CFD) software for nuclear applications. To limit the scope of the effort, the committee will further limit its focus to software to be used in the licensing of High-Temperature Gas-Cooled Reactors. Although software verification will be an important and necessary part of the standard, much of the initial effort of the committee will be focused on the validation of existing software and new models that could be used in the licensing process. In this framework, the Standard should conform to Nuclear Regulatory Commission (NRC) and other regulatory practices, procedures and methods for licensing of nuclear power plants as embodied in the United States (U.S.) Code of Federal Regulations and other pertinent documents such as Regulatory Guide 1.203, “Transient and Accident Analysis Methods” and NUREG-0800, “NRC Standard Review Plan”. In addition, the Standard should be consistent with applicable sections of ASME NQA-1-2008 “Quality Assurance Requirements for Nuclear Facility Applications (QA)”. This paper describes the general

  11. Nuclear reactors' construction costs: The role of lead-time, standardization and technological progress

    International Nuclear Information System (INIS)

    Berthelemy, Michel; Escobar Rangel, Lina

    2013-01-01

    This paper provides the first comparative analysis of nuclear reactor construction costs in France and the United States. Studying the cost of nuclear power has often been a challenge, owing to the lack of reliable data sources and heterogeneity between countries, as well as the long time horizon which requires controlling for input prices and structural changes. We build a simultaneous system of equations for overnight costs and construction time (lead-time) to control for endogeneity, using expected demand variation as an instrument. We argue that benefits from nuclear reactor program standardization can arise through short term coordination gains, when the diversity of nuclear reactors' technologies under construction is low, or through long term benefits from learning spillovers from past reactor construction experience, if those spillovers are limited to similar reactors. We find that overnight construction costs benefit directly from learning spillovers but that these spillovers are only significant for nuclear models built by the same Architect-Engineer (A- E). In addition, we show that the standardization of nuclear reactors under construction has an indirect and positive effect on construction costs through a reduction in lead-time, the latter being one of the main drivers of construction costs. Conversely, we also explore the possibility of learning by searching and find that, contrary to other energy technologies, innovation leads to construction costs increases. (authors)

  12. Absolute locations of the North Korean nuclear tests based on differential seismic travel times and InSAR

    Science.gov (United States)

    Myers, S. C.; Ford, S. R.; Mellors, R. J.; Ichinose, G.

    2017-12-01

    We use constraints on the location of the January 6, 2016 DPRK announced nuclear test (2016_01) and differential travel times for Pn, Pg, and teleseismic P-waves to estimate the absolute locations of the 6 announced DPRK nuclear tests, as well as other nearby events. Absolute location constraints are based on the fit of commercial InSAR-derived ground displacement and predictions of elastic displacement from an isotropic source including topographic effects. Results show that the announced tests in January and September of 2016 are under the crest of highest local topography (Mt. Mantap), while the 2009 and 2013 events are south of the topographic crest at a similar contour in local topography. The first announced test in 2006 was located near the crest of a separate topographic high approximately 2.75 km east of the 2016_01 test. The September 3, 2017 event is approximately between the two 2016 tests, under the crest of the mountain ridge. Constraints from seismic data put the events within 1 km of the surface and depths may be inferred, with caution, by differencing the elevation of tunnel entrances and the topographic surface and accounting for the rise in a tunnel elevation from the entrance to facilitate drainage. Depths for the 2006_10, 2009_05, 2013_02, 2016_01, 2016_09, and 2017_09 tests are estimated to be 500 m, 530 m, 530 m, 740 m, 750 m, and 750 m, respectively. Other nearby events are considerably lower in magnitude, resulting in location estimates that are not as well constrained as the announced nuclear tests. Analysis of all events provides a bulletin of events that may occur in the future. Prepared by LLNL under Contract DE-AC52-07NA27344.

  13. Impact of New Radiation Safety Standards on Licensing Requirements of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Strohal, P.; Subasic, D.; Valcic, I.

    1996-01-01

    As the outcomes of the newly introduced safety philosophies, new and more strict safety design requirements for nuclear installation are expected to be introduced. New in-depth defence measures should be incorporated into the design and operation procedure for a nuclear installation, to compensate for potential failures in protection or safety measures. The new requirements will also apply to licensing of NPP's operation as well as to licensing of nuclear sites, especially for radioactive waste disposal sites. This paper intends to give an overview of possible impacts of new internationally agreed basic safety standards with respect to NPP and related technologies. Recently issued new basic safety standards for radiation protection are introducing some new safety principles which may have essential impact on future licensing requirements regarding nuclear power plants and radioactive waste installations. These new standards recognize exposures under normal conditions ('practices') and intervention conditions. The term interventions describes the human activities that seek to reduce the existing radiation exposure or existing likelihood of incurring exposure which is not part of a controlled practice. The other new development in safety standards is the introduction of so called potential exposure based on the experience gained from a number of radiation accidents. This exposure is not expected to be delivered with certainty but it may result from an accident at a source or owing to an event or sequence of events of a probabilistic nature, including equipment failures and operating errors. (author)

  14. Standardized System of Nuclear Safety Information for the Promotion of Transparency and Openness

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Gihyung; Kim, Sanghyun; Lee, Gyehwi; Yoon, Yeonhwa; Song, Song Hyerim; Jeong, Jina [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Byun, Jaehyung; Seo, Jonghwan [Dong-A Univ., Busan (Korea, Republic of)

    2013-05-15

    There has been an increasing emphasis on the need for increased disclosure of information through the home page of the Korea Institute of Nuclear Safety (KINS), responsible for nuclear safety regulations, and the Nuclear Safety Information Center (NSIC) to enhance public understanding of nuclear safety. However, due to the dazzled structure of the existing KINS and NSIC home pages, improvements in accessibility and convenience are necessary. At the same time, content standardization is required to increase operational efficiency and provide coherent information. In this study, the Delphi method was used to select the major contents to make available on the home page as well as the main user base definition for the home page layout development. Also, internal and external expert groups were created to conduct AHP (Analytic Hierarchy Process) analysis and develop the comparative analysis items for the U. S. Nuclear Regulatory Commission(NRC)/KINS/NSIC home pages. Afterwards, problems and points of improvements for the home page system, design, and profile were derived using heuristic analysis. The implications arising from the Delphi analysis results were applied to the home page layout. In the nuclear safety information standardized system construction process, the comparative analysis conducted using the AHP and heuristic analyses of the NRC home page resulted in deriving improvements for the Guidance, Organization, and Trustworthy items of the KINS/NSIC home page. Furthermore, through the Delphi analysis, a clear purpose and core values were set for the KINS web site, and the needs of the main user base were identified. By developing the home page layout, user interest and utility were raised to improve the organization method and layout. Through this study, KINS was able to construct a nuclear safety information standardized system and increase transparency and openness by providing feature enhancements in information provision as well as user accessibility and

  15. Standardized System of Nuclear Safety Information for the Promotion of Transparency and Openness

    International Nuclear Information System (INIS)

    Lee, Gihyung; Kim, Sanghyun; Lee, Gyehwi; Yoon, Yeonhwa; Song, Song Hyerim; Jeong, Jina; Byun, Jaehyung; Seo, Jonghwan

    2013-01-01

    There has been an increasing emphasis on the need for increased disclosure of information through the home page of the Korea Institute of Nuclear Safety (KINS), responsible for nuclear safety regulations, and the Nuclear Safety Information Center (NSIC) to enhance public understanding of nuclear safety. However, due to the dazzled structure of the existing KINS and NSIC home pages, improvements in accessibility and convenience are necessary. At the same time, content standardization is required to increase operational efficiency and provide coherent information. In this study, the Delphi method was used to select the major contents to make available on the home page as well as the main user base definition for the home page layout development. Also, internal and external expert groups were created to conduct AHP (Analytic Hierarchy Process) analysis and develop the comparative analysis items for the U. S. Nuclear Regulatory Commission(NRC)/KINS/NSIC home pages. Afterwards, problems and points of improvements for the home page system, design, and profile were derived using heuristic analysis. The implications arising from the Delphi analysis results were applied to the home page layout. In the nuclear safety information standardized system construction process, the comparative analysis conducted using the AHP and heuristic analyses of the NRC home page resulted in deriving improvements for the Guidance, Organization, and Trustworthy items of the KINS/NSIC home page. Furthermore, through the Delphi analysis, a clear purpose and core values were set for the KINS web site, and the needs of the main user base were identified. By developing the home page layout, user interest and utility were raised to improve the organization method and layout. Through this study, KINS was able to construct a nuclear safety information standardized system and increase transparency and openness by providing feature enhancements in information provision as well as user accessibility and

  16. The Korean threat steps up a notch

    International Nuclear Information System (INIS)

    Chicheportiche, Romain; Thouverez, Pierre

    2016-01-01

    As North Korea announced a successful test for its first hydrogen nuclear bomb, the author first recalls the origins of the Korean conflict, and then presents the North Korean nuclear weapon programme as a result of a sense of insecurity for the North Korean regime, notably after the collapse of USSR. The nuclear weapon then became a priority and the programme has been rather quickly developed, probably with the help of the father of the Pakistani bomb. A first and second plutonium-based bombs have been tested, and then an enriched uranium-based bomb, and lastly, in January 2016, a hydrogen bomb. Doubts about this achievement are evoked. Then, the author proposes a brief overview of negotiations with the USA, and outlines the problematic behaviour of North Korea regarding the regional situation in an evolving context: a stronger Chinese economy, change in China's position towards North Korea, and Japan re-militarization

  17. Controlling engineering project changes for multi-unit, multi-site standardized nuclear power plants

    International Nuclear Information System (INIS)

    Randall, E.; Boddeker, G.; McGugin, H.; Strother, E.; Waggoner, G.

    1978-01-01

    Multibillioin dollar multiple nuclear power plant projects have numerous potential sources of engineering changes. The majority of these are internally generated changes, client generated changes, and changes from construction, procurement, other engineering organizations, and regulatory organizations. For multiunit, multisite projects, the use of a standardized design is cost effective. Engineering changes can then be controlled for a single standardized design, and the unit or site unique changes can be treated as deviations. Once an effective change procedure is established for change control of the standardized design, the same procedures can be used for control of unit or site unique changes

  18. Technical requirements for the ASME PRA standard for nuclear power plant applications

    International Nuclear Information System (INIS)

    Fleming, Karl N.; Bernsen, Sidney A.; Simard, Ronald L.

    2000-01-01

    In 1998 the American Society of Mechanical Engineers (ASME) formed the Committee on Nuclear Risk Management (CNRM) and a Project Team to develop a standard on PRAs for use in risk informed applications. This ASME standard is being developed to help provide an adequate level of quality in PRAs that are being used to support ASME initiatives to risk informed in-service inspection (ISI) and in-service testing (IST) of nuclear power plant components. A related need supported by the industry and the U.S. Nuclear Regulatory Commission is to reduce the level of effort that is being expended in pilot applications of risk informed initiatives to address questions about the sufficiency of quality in the supporting PRA models. The purpose of this paper is to discuss the authors' views on some of the technical issues that were encountered in the effort to develop the ASME PRA standard. Draft 12 of this standard has been issued for comment, and is currently being finalized with the aim of releasing the standard in early 2001. (author)

  19. Dictionary of the terms on nuclear scientific technique of France and Korea

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1984-09-15

    This book is a dictionary of the terms on nuclear scientific technique, which defines 3,400 terms and phrases in detailed explanation and lists in order of French, Korean and English. The terms are in alphabetical order, which are collision, elastic collision, nuclear fusion, fusion energy, absorption analysis, absorption curve, neutron, nuclear, radiation, radioactivity, reactor, nuclear disintegration, and so on. This book has appendixes on a standard unit, radiation size and unit, and the table of elements.

  20. Dictionary of the terms on nuclear scientific technique of France and Korea

    International Nuclear Information System (INIS)

    1984-09-01

    This book is a dictionary of the terms on nuclear scientific technique, which defines 3,400 terms and phrases in detailed explanation and lists in order of French, Korean and English. The terms are in alphabetical order, which are collision, elastic collision, nuclear fusion, fusion energy, absorption analysis, absorption curve, neutron, nuclear, radiation, radioactivity, reactor, nuclear disintegration, and so on. This book has appendixes on a standard unit, radiation size and unit, and the table of elements.

  1. History of Korean Neurosurgery.

    Science.gov (United States)

    Hwang, Sung-nam

    2015-08-01

    The year 2012 was the 50th anniversary of the Korean Neurosurgical Society, and in 2013, the 15th World Congress of Neurosurgery took place in Seoul, Korea. Thus, it is an appropriate occasion to introduce the world to the history of the Korean Neurosurgical Society and the foundation, development, and growth of Korean neurosurgery. Historical materials and pictures were collected and reviewed from the history book and photo albums of the Korean Neurosurgical Society. During the last 50 years, the Korean Neurosurgical Society and Korean neurosurgery have developed and grown enormously not only in quantity but also in quality. In every aspect, the turning point from the old to the new era of the Korean Neurosurgical Society and Korean neurosurgery was the year 1980. Copyright © 2015. Published by Elsevier Inc.

  2. Methodology to evaluate the site standard seismic motion to a nuclear facility

    International Nuclear Information System (INIS)

    Soares, W.A.

    1983-01-01

    For the seismic design of nuclear facilities, the input motion is normally defined by the predicted maximum ground horizontal acceleration and the free field ground response spectrum. This spectrum is computed on the basis of records of strong motion earthquakes. The pair maximum acceleration-response spectrum is called the site standard seismic motion. An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic principles of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; available methodologies and recommended procedures to evaluate the site standard seismic motion. (Author) [pt

  3. Secondary standard dosimetry laboratory Saraykoy Nuclear Research and Training Center Ankara, Turkey

    International Nuclear Information System (INIS)

    Okruhlica, P.

    2014-01-01

    Turkish Saraykoy Nuclear Research and Training Center (SANA) was founded in 2005. In 2014 the company PTW Freiburg in cooperation with VF Cerna Hora started the construction of a comprehensive national metrology laboratories of ionizing radiation 'Secondary Standard Dosimetry Laboratory' (SSDL). The laboratory will be located in the area of 'Saraykoy Nuclear Research and Training Center' in Ankara in Turkey. SSDL will be equipped with metrology departments for calibration and measurement of standard required quantities of metrology of ionizing radiation: - Neutron workplace; Gamma workplace (low-energy X-ray, gamma Standard Cs-137 and high dose rate, Co-60); - Beta workplace; - Control system of metrology laboratories and irradiation VF DARS; - Radiation monitoring system VF RMS; - Camera and security system; - Measuring instruments (ionization chambers, electrometers, monitors for environmental measurements ...) with the appropriate phantoms and other systems.

  4. Fundaments for creation of national radiation protection standard for nuclear gauges

    International Nuclear Information System (INIS)

    Ferreira, Luiz Cavalcante

    2016-01-01

    The present work It aims to provide fundaments for the creation of a national standard of practice, safety and responsible use of nuclear gauges in accordance with the recommendations already existing national and international. The work deals with the protection against ionizing radiation, an outline of a proposal for a standard that discriminates in its articles and paragraphs, the basic principles of a proposal for a standard that discriminates in its articles and paragraphs, the basic principles of safety and security, and some pointes that are also relevant such as the responsibilities of those involved in acquisition and nuclear gauge operation, storage, maintenance, testing and emergency situations. The result is to provide a means to limit the dose of operators and people from the public and maintain these limits within the recommended by CNEN, reducing exposure do ionizing radiation, and having greater control in operating the equipment. (author)

  5. The EU’s Potential Role in the Six Party Talks and the North Korean Nuclear Crisis

    Directory of Open Access Journals (Sweden)

    Millard Andrew S.

    2017-10-01

    Full Text Available Discourse on the Six Party Talks has focused solely on denuclearisation. Through the power struggles of the members and the refusal of the People’s Democratic Republic of Korea (DPRK to return to negotiations, the Six Party Talks have been stalled since 2008. Due to current increased tensions and the use of brinkmanship tactics the Talks must be restarted, albeit under a reformed shape. This paper analyses the potential role of the EU in furthering the peace process in Northeast Asia. This paper suggests that the EU needs to be more assertive and the Talks should focus on building trust and cooperation, not on the DPRK’s nuclear program. With its impartiality, experience in integration and use of soft power, the EU can act as an effective mediator building trust.

  6. An investigation on unintended reactor trip events in terms of human error hazards of Korean nuclear power plants

    International Nuclear Information System (INIS)

    Kim, Sa Kil; Lee, Yong Hee; Jang, Tong Il; Oh, Yeon Ju; Shin, Kwang Hyeon

    2014-01-01

    Highlights: • A methodology to identify human error hazards has been established. • The proposed methodology is a preventive approach to identify not only human error causes but also its hazards. • Using the HFACS framework we tried to find out not causations but all of the hazards and relationships among them. • We determined countermeasures against human errors through dealing with latent factors such as organizational influences. - Abstract: A new approach for finding the hazards of human errors, and not just their causes, in the nuclear industry is currently required. This is because finding causes of human errors is really impossible owing to the multiplicity of causes in each case. Thus, this study aims at identifying the relationships among human error hazards and determining the strategies for preventing human error events by means of a reanalysis of the reactor trip events in Korea NPPs. We investigated human errors to find latent factors such as decisions and conditions in all of the unintended reactor trip events during the last dozen years. In this study, we applied the HFACS (Human Factors Analysis and Classification System), which is a commonly utilized tool for investigating human contributions to aviation accidents under a widespread evaluation scheme. Using the HFACS framework, we tried to find out not the causations but all of the hazards and their relationships in terms of organizational factors. Through the trial, we proposed not only meaningful frequencies of each hazards also correlations of them. Also, considering the correlations of each hazards, we suggested useful strategies to prevent human error event. A method to investigate unintended nuclear reactor trips by human errors and the results will be discussed in more detail

  7. Review of international standards related to the design for control rooms on nuclear power plants

    International Nuclear Information System (INIS)

    Kitamura, Masashi; Yoshikawa, Hidekazu; Fujita, Yushi

    2005-01-01

    The improvement of Human-Machine Interface (HMI) design for control rooms on nuclear power plants (NPP) has been accomplished world wide, especially after the TMI-2 accident. The design process and guidelines are standardized in IEC60964 and supplemental standards as international standard. However, technological update is required due to the increased use of computerized control and monitoring equipment and systems in control rooms on NPP in recent years. Standards are becoming more important for computerized control rooms because there is more freedom to design than conventional hardware based system. For computerized control rooms, standards for hardware and software of HMI systems should be also considered. Standards and guidelines for computerized control rooms on NPP have been developed recently in each body such as IEC, ISO, and IEEE etc. Therefore, reviewing these standards and guidelines related to control rooms design of NPP can be useful not only for revision of the international standards such as IEC60964, but also for users of the standards and guidelines. In this paper, we reviewed the international standards related to the design for control rooms, in the two aspects of HMI design and hardware and software design, considering the undergoing revision work and their application. (author)

  8. New requirements on safety of nuclear power plants according to the IAEA safety standards

    International Nuclear Information System (INIS)

    Misak, J.

    2005-01-01

    In this presentation author presents new requirements on safety of nuclear power plants according to the IAEA safety standards. It is concluded that: - New set of IAEA Safety Standards is close to completion: around 40 standards for NPPs; - Different interpretation of IAEA Safety Standards at present: best world practices instead of previous 'minimum common denominator'; - A number of safety improvements required for NPPs; - Requirements related to BDBAs and severe accidents are the most demanding due to degradation of barriers: hardware modifications and accident management; - Large variety between countries in implementation of accident management programmes: from minimum to major hardware modifications; -Distinction between existing and new NPPs is essential from the point of view of the requirements; WWER 440 reactors have potential to reflect IAEA Safety Standards for existing NPPs; relatively low reactor power offers broader possibilities

  9. Development of a standard communication protocol for an emergency situation management in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Man Cheol, E-mail: charleskim@kaeri.re.k [Integrated Risk Assessment Center, Korea Atomic Energy Research Institute, 150, Deokjin-dong, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Park, Jinkyun; Jung, Wondea [Integrated Risk Assessment Center, Korea Atomic Energy Research Institute, 150, Deokjin-dong, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Kim, Hanjeom; Kim, Yoon Joong [YGN Nuclear Power Division Training Center, Korea Hydro and Nuclear Power Company, 517 Kyemari, Hongnong-eup, Yeongkwang-gun, Chonnam 513-880 (Korea, Republic of)

    2010-06-15

    Correct communication between main control room (MCR) operators is an important factor in the management of emergency situations in nuclear power plants (NPPs). For this reason, a standard communication protocol for the management of emergency situations in NPPs has been developed, with the basic direction of enhancing the safety of NPPs and the standardization of communication protocols. To validate the newly developed standard communication protocol, validation experiments with 10 licensed NPP MCR operator teams was performed. From the validation experiments, it was found that the use of the standard communication protocol required more time, but it can contribute to the enhancement of the safety of NPPs by an operators' better grasp of the safety-related parameters and a more efficient and clearer communication between NPP operators, while imposing little additional workloads on the NPP MCR operators. The standard communication protocol is expected to be used to train existing NPP MCR operators without much aversion, as well as new operators.

  10. Development of standard technical report on using and selecting wireless device in nuclear power plants

    International Nuclear Information System (INIS)

    Koo, I. S.; Hong, S. B.; Cho, J. W.

    2011-11-01

    1. Purpose · Development of IEC technical report on wireless device using in nuclear power plants 2. Contents · IEC technical reports of draft for circulation and final draft for next planary meeting · Case study on experiment of wireless devices 3. Implementation methods · Preparation of first draft with experts group, its circulation, discussions on the results of the circulation · Organizing three teams such as preparation, reviews and experiment 4. Results · Maintenance cost will be reduced with application of the wireless technologies in nuclear power plants · Commercial wireless devices will be developed before standard is issued

  11. Standardization of the Korean version of Mini-Mental Adjustment to Cancer (K-Mini-MAC) scale: factor structure, reliability and validity.

    Science.gov (United States)

    Kang, Jee In; Chung, Hyun Cheol; Kim, Se Joo; Choi, Hye Jin; Ahn, Joong Bae; Jeung, Hei-Cheul; Namkoong, Kee

    2008-06-01

    Mental adjustment and coping affect the physical outcome and survival as well as quality of life in cancer patients. The Mini-Mental Adjustment to Cancer (Mini-MAC) scale is a new refined, economical and reliable self-rating instrument measuring cognitive and behavioral responses to cancer. The aim of this study was to evaluate the psychometric properties of the Mini-MAC in Korean cancer patients. A total of 208 cancer patients recruited from the Yonsei Cancer Center were assessed with the Mini-MAC and the Hospital Anxiety and Depression Scale (HADS). Principal component analysis with varimax rotation for the Korean version of Mini-MAC (K-Mini-MAC) confirmed four factors. Three had psychometric properties similar to Helpless-Hopeless (HH), Anxious Preoccupation (AP) and Cognitive Avoidance (CA) of the original Mini-MAC. A novel factor, named Positive Attitude, included items of both Fatalism (FA) and Fighting Spirit (FS) from the original version. The five subscales from the original version (AP, HH, FS, FA and CA) and Positive Attitude had acceptable internal reliabilities in our sample (Cronbach's alpha coefficient 0.50-0.86; correlation coefficient of test-retest 0.68-0.88). For the validity, significant interscale correlation was observed in the original five subscales and Positive Attitude. Each subscale including Positive Attitude was also significantly related to Depression and Anxiety of HADS. As a whole, the K-Mini-MAC was a reliable, valid and acceptable tool for Korean cancer patients. These findings can provide information about the cross-cultural validity of Mini-MAC scale's factor structure. Cultural differences were also discussed.

  12. Principles and objectives for the operation and support of standard nuclear plants

    International Nuclear Information System (INIS)

    1994-08-01

    This publication provides the guiding principles and objectives for the operation and support of standard nuclear plants. They are the basis for designing the processes to operate and support the new plants and to estimate the staffing options. INPO has facilitated and coordinated the development of these principles and objectives under the industry's Strategic Plan for Building New Nuclear Power Plants. The industry's plan, first published in 1990, designates INPO as the lead in achieving the following goals: 1. Establish an institutional framework and approach to implement and maintain a model for life-cycle standardization of a family of plants. 2. Develop standardization objectives and selected standardized function and process descriptions to provide a basis for uniformity in appropriate aspects of the organizational structure; administrative controls; and construction, startup, operating, and maintenance practices. 3. Develop an approach to maintain the standard design and design intent as well as standardized operational approaches in all units within a family of plants over their lifetimes. This document supports these goals. Twelve guiding principles are followed by descriptions of four functions, and after that eight processes with their associated objectives

  13. Co-operative development of nuclear safety regulations, guides and standards based on NUSS

    International Nuclear Information System (INIS)

    Pachner, J.; Boyd, F.C.; Yaremy, E.M.

    1985-01-01

    A major need of developing Member States building nuclear power plants (NPPs) of foreign origin is to acquire a capability to regulate such nuclear plants independently. Among other things, this requires the development of national nuclear safety regulations, guides and standards to govern the development and use of nuclear technology. Recognizing the importance and complexity of this task, it seems appropriate that the NPP-exporting Member States share their experience and assist the NPP-importing Member States in the development of their national regulations and guides. In 1983, the Atomic Energy Control Board and Atomic Energy of Canada Ltd. conducted a study of a possible joint programme involving Canada, an NPP-importing Member State and the IAEA for the development of the national nuclear safety regulations and guides based on NUSS documents. During the study, a work plan with manpower estimates for the development of design regulations, safety guides and a guide for regulatory evaluation of design was prepared as an investigatory exercise. The work plan suggests that a successful NUSS implementation in developing Member States will require availability of significant resources at the start of the programme. The study showed that such a joint programme could provide an effective mechanism for transfer of nuclear safety know-how to the developing Member States through NUSS implementation. (author)

  14. Activity of the Atomic Energy Society of Japan for compiling the consensus standard on nuclear criticality safety control

    International Nuclear Information System (INIS)

    Yamane, Yoshihiro; Matsumoto, Tadakuni

    2003-01-01

    Activity of the Atomic Energy Society of Japan for compiling the consensus standard on nuclear criticality safety control is presented. The standard recommends an enhancement of nuclear criticality safety throughout a life cycle of facility in terms of a concept of 'barriers against criticality'. (author)

  15. Integrated framework for the external cost assessment of nuclear power plant accident considering risk aversion: The Korean case

    International Nuclear Information System (INIS)

    Lee, Sang Hun; Kang, Hyun Gook

    2016-01-01

    Recently, the estimation of accident costs within the social costs of nuclear power plants (NPPs) has garnered substantial interest. In particular, the risk aversion behavior of the public toward an NPP accident is considered an important factor when integrating risk aversion into NPP accident cost. In this study, an integrated framework for the external cost assessment of NPP accident that measures the value of statistical life (VSL) and the relative risk aversion (RRA) coefficient for NPP accident based on an individual-level survey is proposed. To derive the willingness to pay and the RRA coefficient for NPP accident risks, a survey was conducted on a sample of 1550 individuals in Korea. The estimation obtained a mean VSL of USD 2.78 million and an RRA coefficient of 1.315. Based on the estimation results in which various cost factors were considered, a multiplication factor of 5.16 and an external cost of NPP accidents of 4.39E−03 USD-cents/kW h were estimated. This study is expected to provide insight to energy policy decision-makers on analyzing the economic validity of NPP compared to other energy sources by reflecting the estimated external cost of NPP accident into the unit electricity generation cost of NPP. - Highlights: •External cost assessment framework for NPP is proposed considering risk aversion. •VSL was derived from WTP for mortality risk reduction from hypothetical NPP accident. •RRA was derived to integrate public risk aversion into external cost of NPP accident. •Individual-level survey was conducted to derive WTP and RRA for NPP accident risk. •The external cost was estimated considering the direct cost factors of NPP accident.

  16. Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal. 1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations. 1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams. 1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams. 1.5 This standard does not purport to address ...

  17. A scheme for the audit of scientific and technological standards in clinical nuclear medicine

    International Nuclear Information System (INIS)

    Perkins, A.C.; Jarritt, P.H.

    2002-01-01

    Aim: Audit is the process whereby the quality of a service is monitored and optimised. It forms an essential component of the quality assurance process, whether by self-assessment or by external peer review. In the UK the British Nuclear Medicine Society (BNMS) has undertaken external organisational audit of departments providing clinical nuclear medicine services. This work aimed to develop a more thorough and service specific process for the audit of scientific and technological standards in nuclear medicine. Materials and Methods: The audit process has been implemented using written audit documents to facilitate the audit procedure. A questionnaire forms part of the formal documentation for audit of the scientific and technical standards of a clinical service. Scientific and technical standards were derived from a number of sources including legal requirements, regulatory obligations, notes for guidance, peer reviewed publications and accepted good clinical practice (GCP). Results: The audit process graded the standards of an individual department according to legal or safety requirements (Grade A), good practice (Grade B) and desirable aspects of service delivery (Grade C). The standards have been allocated into eight main categories. These are: Instrumentation; Software and data protection; Electrical Safety; Mechanical Safety; Workstation Safety; The Control of Substances Hazardous to Health (COSHH); Radiation Protection; Scientific and Technical staffing levels. During the audit visit a detailed inspection of clinical and laboratory areas and department written documentation is also necessary to validate the data obtained. Conclusion: The printed scheme now provides a means for external audit or self-assessment. There should be evidence of a well-organised and safe environment for both patients and staff. Health and Safety legislation requires written local rules and these records should be available to demonstrate the standard of service provision. Other

  18. Restructuring of technical standards for regulation of nuclear power plants in Japan

    International Nuclear Information System (INIS)

    Takehiko Nakamura; Masahiro Aoki; Kiyoshi Takasaka; Yukio Hirano; Eiji Hiraoka; Mikio Kurihara; Junichi Morita; Zenichi Ogiso; Yoshihiko Nishiwaki

    2005-01-01

    Regulatory requirements for nuclear power plants (NPPs) have been reviewed and restructured in Japan, in order to accommodate recent technical progress in a timely manner. In this new regulatory process, the governmental technical requirements are modified to performance specifications and the consensus codes and standards established by academic and public societies are being used as prescriptive specifications to realize the performance. As a first step, a fitness-rule to evaluate structural integrity of the components having cracks was introduced into the Japanese regulatory rules in Oct. 2003. 'Rules on Fitness-for-Service for Nuclear Power Plants' by the Japan Society of Mechanical Engineers (JSME) was utilized as a prescriptive specification for in-service-inspections and for the integrity evaluation of the components with stress corrosion cracks and fatigue cracks. The process is being extended to other requirements for structural design and construction of mechanical components and concrete containments, as well as requirements for welding. Prescriptive specifications for the requirements by the JSME and other consensus codes have been technically reviewed by a regulatory body, the Nuclear and Industrial Safety Agency, and specified as regulatory standards for the licensing procedure. In the course of the review, consistency and coverage of the requirements were examined against the Safety Design Guidelines by the Nuclear Safety Commission and the safety requirements for design of nuclear power plant by the International Atomic Energy Agency, NS-R-1. Additional requirements against the stress corrosion cracking, hydrogen accumulation, high-cycle thermal fatigue, etc. are being specified in the requirements to prevent troubles experienced in NPPs in Japan and overseas. This paper describes outlines of the on-going activities restructuring the technical standards for regulation of NPPs in Japan. (authors)

  19. Environmental Standard Review Plan for the review of license renewal applications for nuclear power plants

    International Nuclear Information System (INIS)

    O'Brien, J.; Kim, T.J.; Reynolds, S.

    1991-08-01

    The Environmental Standard Review Plan for the Review of License Applications for Nuclear Power Plants (ESRP-LR) is to be used by the NRC staff when performing environmental reviews of applications for the renewal of power reactor licenses. The use of the ESRP-LR provides a framework for the staff to determine whether or not environmental issues important to license renewal have been identified and the impacts evaluated and provides acceptance standards to help the reviewers comply with the National Environmental Policy Act

  20. Standard protocol for conducting pre-operational environmental surveillance around nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Hegde, A G; Verma, P C; Rajan, M P [Health Safety and Environment Group, Bhabha Atomic Research Centre, Mumbai (India)

    2009-02-15

    This document presents the standard procedures for evaluation of site specific environmental transfer factors around NPP sites. The scope of this document is to provide standard protocol to be followed for conducting pre-operational environmental surveillance around nuclear facilities. Such surveillances have been proposed to be carried out by university professionals under DAE-BRNS projects. This document contains a common methodology in terms of sampling, processing, measurements and analysis of elemental/radionuclides, while keeping the site specific requirements also in place. (author)

  1. Standard protocol for conducting pre-operational environmental surveillance around nuclear facilities

    International Nuclear Information System (INIS)

    Hegde, A.G.; Verma, P.C.; Rajan, M.P.

    2009-02-01

    This document presents the standard procedures for evaluation of site specific environmental transfer factors around NPP sites. The scope of this document is to provide standard protocol to be followed for conducting pre-operational environmental surveillance around nuclear facilities. Such surveillances have been proposed to be carried out by university professionals under DAE-BRNS projects. This document contains a common methodology in terms of sampling, processing, measurements and analysis of elemental/radionuclides, while keeping the site specific requirements also in place. (author)

  2. Analyses of the phosphate standard of the Egyptian Nuclear Materials Corp. (phosphate-1)

    Energy Technology Data Exchange (ETDEWEB)

    Aly, M M

    1986-01-01

    A new whole rock phosphorite has been prepared in the Nuclear Materials Corp. Egypt. This is a part of the Egytian N.M.C. program to prepare a series of rock standards. This program began in 1983 to fulfil the continuous demand for such standards in all the research laboratories. Statistical analysis for silica, phosphorus, calcium, iron and strontium in selected fractions of this rock showed the homogeneity of the sample. Conventional methods, as well as rapid analysis, inductively coupled plasma spectrometry, X-ray fluorescence, activation analysis, i.r. spectroscopy, atomic absorption and laser induced fluorescence techniques have been used to give a complete chemical characterization of the sample.

  3. Standard specification for nuclear-grade silver-indium-cadmium alloy

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2003-01-01

    1.1 This specification covers silver-indium-cadmium alloy for use as a control material in light-water nuclear reactors. 1.2 The scope of this specification excludes the use of this material in applications where material strength of this alloy is a prime requisite. Also, this material must be protected from the primary water by a corrosion and wear resistant cladding. 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

  4. Replacement power costs due to nuclear-plant outages: a higher standard of care

    International Nuclear Information System (INIS)

    Gransee, M.F.

    1982-01-01

    This article examines recent state public utility commission cases that deal with the high costs of replacement power that utilities must purchase after a nuclear power plant outage. Although most commissions have approved such expenses, it may be that there is a trend toward splitting the costs of such expenses between ratepayer and stockholder. Commissions are demanding a management prudence test to determine the cause of the outage and whether it meets the reasonable man standard before allowing these costs to be passed along to ratepayers. Unless the standard is applied with flexibility, however, utility companies could invoke the defenses covering traditional common law negligence

  5. Fundamental challenging problems for developing new nuclear safety standard computer codes

    International Nuclear Information System (INIS)

    Wong, P.K.; Wong, A.E.; Wong, A.

    2005-01-01

    Based on the claims of the US Basic patents number 5,084,232; 5,848,377 and 6,430,516 that can be obtained from typing the Patent Numbers into the Box of the Web site http://164.195.100.11/netahtml/srchnum.htm and their associated published technical papers having been presented and published at International Conferences in the last three years and that all these had been sent into US-NRC by E-mail on March 26, 2003 at 2:46 PM., three fundamental challenging problems for developing new nuclear safety standard computer codes had been presented at the US-NRC RIC2003 Session W4. 2:15-3:15 PM. at the Washington D.C. Capital Hilton Hotel, Presidential Ballroom on April 16, 2003 in front of more than 800 nuclear professionals from many countries worldwide. The objective and scope of this paper is to invite all nuclear professionals to examine and evaluate all the current computer codes being used in their own countries by means of comparison of numerical data from these three specific openly challenging fundamental problems in order to set up a global safety standard for all nuclear power plants in the world. (authors)

  6. Qualification of Programmable Electronic System (PES) equipment based on international nuclear I and C standards

    International Nuclear Information System (INIS)

    De Grosbois, J.; Hepburn, G. A.; Olmstead, R.; Goble, W.; Kumar, V.

    2006-01-01

    Nuclear power plants (NPPs) are increasingly faced with the challenge of qualifying procured equipment, sub-components, and systems that contain digital programmed electronics for use in safety-related applications. Referred to as a 'programmable electronic system' (PES), such equipment typically contains both complex logic that is vulnerable to systematic design faults, and low voltage electronics hardware that is subject to random faults. Procured PES products or components are often only commercial grade, yet can offer reliable cost effective alternatives to custom-designed or nuclear qualified equipment, provided they can be shown to meet the quality assurance, functional safety, environmental, and reliability requirements of a particular application. The process of confirming this is referred to as application-specific product qualification (ASPQ) and can be challenging and costly. This paper provides an overview of an approach that has been developed at Atomic Energy Canada Limited (AECL) and successfully applied to PES equipment intended for use in domestic Candu R 6 nuclear power plants and special purpose reactors at Chalk River Laboratories. The approach has evolved over the past decade and has recently been adapted to be consistent with, and take advantage of new standards that are applicable to nuclear safety-related I and C systems. Also discussed are how recognized third-party safety-certifications of PES equipment to International Electrotechnical Commission (IEC) standards, and the assessment methods employed, may be used to reduce ASPQ effort. (authors)

  7. Standard protocol for demographic and epidemiological survey to be carried out for nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Joshi, M L; Datta, D; Singh, Jitendra; Sardhi, I V; Verma, P C [Health Physics Division, Bhabha Atomic Research Centre, Mumbai (India)

    2007-11-15

    This document presents the standard procedures for conducting demographic and epidemiological studies for nuclear facilities. These studies are required to be carried out to prepare baseline data, the impact of the facility and the risk factors for the population residing in the vicinity of facility. This document includes the basic elements of these type surveys, their methodology and statistical analysis of the data collected during demographic and epidemiological surveillance. (author)

  8. Standard protocol for demographic and epidemiological survey to be carried out for nuclear facilities

    International Nuclear Information System (INIS)

    Joshi, M.L.; Datta, D.; Singh, Jitendra; Sardhi, I.V.; Verma, P.C.

    2007-11-01

    This document presents the standard procedures for conducting demographic and epidemiological studies for nuclear facilities. These studies are required to be carried out to prepare baseline data, the impact of the facility and the risk factors for the population residing in the vicinity of facility. This document includes the basic elements of these type surveys, their methodology and statistical analysis of the data collected during demographic and epidemiological surveillance. (author)

  9. Contributions of the ORNL piping program to nuclear piping design codes and standards

    International Nuclear Information System (INIS)

    Moore, S.E.

    1975-11-01

    The ORNL Piping Program was conceived and established to develop basic information on the structural behavior of nuclear power plant piping components and to prepare this information in forms suitable for use in design analysis and codes and standards. One of the objectives was to develop and qualify stress indices and flexibility factors for direct use in Code-prescribed design analysis methods. Progress in this area is described

  10. A basic study for development of environmental standard review plan of Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Chang Hyun; Cho, Jae Seon; You, Young Woo [Seoul Nationl Univ., Seoul (Korea, Republic of)] (and others)

    1999-12-15

    In this study is performed a basic study to be ready for the development and detail analysis of NUREG-1555 ESRP. As a fundamental research for literature survey and development of draft review plan, review and translation of NUREG-1555 published by NRC, and which is applied to licensing procedure of Nuclear Power Plants are included. These provided the basic information for the developments of the environmental standard review plan.

  11. Aesthetics of Korean foods: The symbol of Korean culture

    Directory of Open Access Journals (Sweden)

    Hae-Kyung Chung

    2016-09-01

    Full Text Available Advances in transportation and communication have broken down critical barriers within the global economy, pushing us towards a more unified world. In keeping with this trend, processes of communication, transportation, and production are becoming increasingly standardized, mechanized, and automated. Yet as this global era of uniformity progresses, people and individuals will inevitably encounter identity confusion. Numerous individuals, ethnicities, nationalities, and countries around the world are working to counteract such identity confusion. As globalization progresses, groups and nationalities that fail to preserve their identities will dwindle and become absorbed by stronger entities. Therefore, many societies are investing great efforts into rediscovering and revamping their indigenous traditions, cultures, and customs. When travelers visit another country, one of the simplest avenues for them to experience the local culture is food. Unlike other cultural elements, many of which have become diluted because of globalization, native cuisines are still perceived as retaining the traditions, uniqueness, and diversity of individual cultures. It is more important than ever for people and countries to expand and preserve their respective cultural currencies. In this respect, taking a cultural approach to Korean cuisine is a fascinating and meaningful endeavor. In light of the recent publication of a few articles dealing with the symbolic significance and meaning behind Korean cuisine, an effort to compile a list of the distinctive cultural properties of Korean food seems vital. Furthermore, presenting the aesthetics of Korean food through a method that integrates science and culture is a very significant task. The authors of this paper firmly believe in its potential to advance the globalization of Korean food.

  12. Applicability of ISO 9001: 2000 standard to design and research activities in nuclear objectives and installations

    International Nuclear Information System (INIS)

    Stamatopol, M.; Patticu, C.

    2001-01-01

    The ISO 9001: 2000 standard contains the results of the latest studies concerning the design and implementation of quality management systems. The continuous improvement of these systems required a new approach, namely, the process-based approach. A process-based model of quality management is presented in terms of client request, input data, management responsibility, resource management, product realisation, measurement / analysis and optimization, product, output data and client request fulfilment. Thus, the quality management system becomes an ensemble of interconnected or interacting processes. Consequently, to implement such a system the necessary processes have to be identified and their ISO 9001: 2000 standard based management ensured. Process based approach also allows better evidencing the input and output data specific to each process. Such an approach grants a wider applicability to the design and research activities in nuclear objectives and installations. This work aims at identifying additional requirements implied in design and research activities in nuclear field, as stipulated in the following standards / documents: - IAEA SG Q8 'Quality assurance in research and development'; - IAEA SG Q10 'Quality assurance in design'; - CAN / CSA N 286.2 - 00 'Design Quality Assurance for Nuclear Power Plants'; CAN 3 - CSA Z 299.1 'Quality Assurance Program - Category 1'; - NQA - 1, SUPPLEMENT 3S-1 'Supplementary requirements for design control'

  13. Standardization and Economics of Nuclear Spacecraft, Final Report, Phase I, Sense Study

    Energy Technology Data Exchange (ETDEWEB)

    1973-03-01

    Feasibility and cost benefits of nuclear-powered standardized spacecraft are investigated. The study indicates that two shuttle-launched nuclear-powered spacecraft should be able to serve the majority of unmanned NASA missions anticipated for the 1980's. The standard spacecraft include structure, thermal control, power, attitude control, some propulsion capability and tracking, telemetry, and command subsystems. One spacecraft design, powered by the radioisotope thermoelectric generator, can serve missions requiring up to 450 watts. The other spacecraft design, powered by similar nuclear heat sources in a Brayton-cycle generator, can serve missions requiring up to 21000 watts. Design concepts and trade-offs are discussed. The conceptual designs selected are presented and successfully tested against a variety of missions. The thermal design is such that both spacecraft are capable of operating in any earth orbit and any orientation without modification. Three-axis stabilization is included. Several spacecraft can be stacked in the shuttle payload compartment for multi-mission launches. A reactor-powered thermoelectric generator system, operating at an electric power level of 5000 watts, is briefly studied for applicability to two test missions of divers requirements. A cost analysis indicates that use of the two standardized spacecraft offers sizable savings in comparison with specially designed solar-powered spacecraft. There is a duplicate copy.

  14. Standard for administration of stable iodine pilulae. Standard of the nuclear safety commission, action for accident in TEPCO Fukushima-1 and recent European trends

    International Nuclear Information System (INIS)

    Ishihara, Hiroshi

    2011-01-01

    Preventive taking of stable-iodine tablets is effective to avoid thyroid gland disorder due to internal exposure to the radioactive iodine if radioactive iodine is released outside by any nuclear accident. In Japan, the Nuclear Safety Commission proposed the standard of the preventive taking in 2002, and, at the Fukushima Daiichi nuclear disaster, the head of the local task force instructed to take on the recommendation from the Commission. Author described the action principle of stable-iodine tablets, present concept for the preventive taking, recent change of the concept in Europe for the preventive taking, and some precepts which have shown in past Fukushima Daiichi nuclear disaster. (J.P.N.)

  15. PHITS code improvements by Regulatory Standard and Research Department Secretariat of Nuclear Regulation Authority

    International Nuclear Information System (INIS)

    Goko, Shinji

    2017-01-01

    As for the safety analysis to be carried out when a nuclear power company applies for installation permission of facility or equipment, business license, design approval etc., the Regulatory Standard and Research Department Secretariat of Nuclear Regulation Authority continuously conducts safety research for the introduction of various technologies and their improvement in order to evaluate the adequacy of this safety analysis. In the field of the shielding analysis of nuclear fuel transportation materials, this group improved the code to make PHITS applicable to this field, and has been promoting the improvement as a tool used for regulations since FY2013. This paper introduced the history and progress of this safety research. PHITS 2.88, which is the latest version as of November 2016, was equipped with the automatic generation function of variance reduction parameters [T-WWG] etc., and developed as the tool equipped with many effective functions in practical application to nuclear power regulations. In addition, this group conducted the verification analysis against nuclear fuel packages, which showed a good agreement with the analysis by MCNP, which is extensively used worldwide and abundant in actual results. It also shows a relatively good agreement with the measured values, when considering differences in analysis and measurement. (A.O.)

  16. Report from the research committee of digital imaging standardization in nuclear medicine

    International Nuclear Information System (INIS)

    Nakamura, Yutaka; Ise, Toshihide; Isetani, Osamu; Ichihara, Takashi; Ohya, Nobuyoshi; Kanaya, Shinichi; Fukuda, Toshio; Horii, Hitoshi.

    1994-01-01

    Since digital scintillation camera systems were developed in 1982, digital imaging is rapidly replacing analog imaging. During the first year, the research committee of digital imaging standardization has collected and analyzed basic data concerning digital examination equipment systems, display equipments, films, and hardware and software techniques to determine items required for the standardization of digital imaging. During the second year, it has done basic phantom studies to assess digital images and analyzed the results from both physical and visual viewpoints. On the basis of the outcome of the research committee's activities and the nationwide survey, the draft of digital imaging standardization in nuclear medicine has been presented. In this paper. the analytical data of the two-year survey, made by the research committee of digital imaging standardization, are presented. The descriptions are given under the following four items: (1) standardization digital examination techniques, (2) standardization of display techniques, (3) the count and pixel of digital images, and (4) standardization of digital imaging techniques. (N.K.)

  17. A Study on the Korean Medicine Education and the Changes in the Traditional Korean Medicine during the Japanese Colonial Era: Focused on the Korean Medicine Training Schools.

    Science.gov (United States)

    Huang, Yongyuan

    2018-04-01

    standard education of Korean medicine but also aimed to lay their foundation in the education system of the Western medical science by forming the separated curriculum including basic medical science, diagnosis, clinic, drug, and the practice of acupuncture and moxibustion. Furthermore, having contained the basic subjects of the Western medical science - physiology, anatomy, pathology, etc. - in the compulsory subjects shows perceiving the intellectual and systematic hegemony of the Western medical science and satisfying the demand of the colonial power. Such an education system was succeeded and solidified through the training sessions and the training schools operated by the local colonial governments after the 1930s. Korean medicine became different from the traditional Korean medicine through the establishment and the operation of such training schools.

  18. Studies on the reference Korean and estimation of radiation exposure dose

    International Nuclear Information System (INIS)

    Kim, Y.J.; Lee, K.S.; Chun, K.J.; Kim, J.B.; Chung, G.H.; Kim, S.R.

    1982-01-01

    For the purpose of establishment of Reference Korean and estimation of internal and external exposure doses in the Reference Korean, we have surveyed reference values for Koreans such as physical standards including height, weight, and body surface area, food consumption rate of daily intake of radioactive substances and exposure dose from natural radiation. (Author)

  19. Topical opinion paper - Apparent Discrepancies Between Nuclear and Conventional Seismic Standards

    International Nuclear Information System (INIS)

    Donald, John; Smith, Ian

    2003-01-01

    The differences between nuclear and conventional seismic standards are considered and their potential significance discussed. The approach to the design of nuclear facilities is appropriately both more rigorous and conservative than that required by conventional seismic standards and codes. For nuclear seismic design the requirements can be presented as assessment principles, e.g., NII SAPs or a safety guide e.g. IAEA; Seismic Design and Qualification for Nuclear Power Plants. The adoption of novel methods or designs are required to be supported by appropriate research and development with the ability to cite a precedent within the industry being a powerful endorsement. The method adopted must reliably predict the seismic response of the item to be qualified, including the seismic response of attached or supported Structures, Systems and Components. (SSC's) The traditional method adopted for seismic qualification by analysis has been based on linear elastic analyses. This is justified on the basis that the response is reliably predicted and realistic, provided that the elements remain elastic. In contrast the benefit of ductile behaviour of conventional structures within the design envelope has long been recognised and used as the basis to justify significant reductions in the seismic demand. Provided the acceptance criteria are met, the SAPs do not preclude and the IAEA safety guide specifically permits non linear behaviour within the design envelope for category 1 items. Both the current nuclear practice and the current conventional seismic standards can be classified as 'force based'. The displacement based approach, also referred to as performance based engineering (PBE), has been developed as a powerful tool in the evaluation and seismic retrofit of existing structures. This approach could be equally valid to the design of new structures and can be used to represent elastic or non linear behaviour although the full benefit will only be realised in the latter

  20. Developing glovebox robotics to meet the national robot safety standard and nuclear safety criteria

    International Nuclear Information System (INIS)

    McMahon, T.T.; Sievers, R.H.

    1991-09-01

    Development of a glove box based robotic system by the Lawrence Livermore National Laboratory (LLNL) is reported. Safety issues addressed include planning to meet the special constraints of operations within a hazardous material glove box and with hostile environments, compliance with the current and draft national robotic system safety standards, and eventual satisfaction of nuclear material handling requirements. Special attention has been required for the revision to the robot and control system models which antedate adoption of the present national safety standard. A robotic test bed, using non-radioactive surrogates is being activated at the Lawrence Livermore National Laboratory to develop the material handling system and the process interfaces for future special nuclear material processing applications. Part of this effort is to define, test, and revise adequate safety controls to ensure success when the system is eventually deployed at a DOE site. The current system is primarily for demonstration and testing, but will evolve into the baseline configuration from which the production system is to be derived. This results in special hazards associated with research activities which may not be present on a production line. Nuclear safety is of paramount importance and has been successfully addressed for 50 years in the DOE weapons production complex. It carries its particular requirements for robot systems and manual operations, as summarized below: Criticality must be avoided (materials cannot consolidate or accumulate to approach a critical mass). Radioactive materials must be confined. The public and workers must be protected from accountable radiation exposure. Nuclear material must be readily retrievable. Nuclear safety must be conclusively demonstrated through hazards analysis. 7 refs

  1. Understanding Korean food culture from Korean paintings

    OpenAIRE

    Hae Kyung Chung; Kyung Rhan Chung; Hung Ju Kim

    2016-01-01

    Background: In Korea, there are many traditional foods that have developed along with the country's rich history. In addition, various food cultures have developed through agricultural traditions, ritual ceremonies, and the sharing of affection. Paintings, works of calligraphy, and music demonstrate some of these cultural characteristics of Korean foods. Further research and analysis of Korean food culture using these data sources is currently underway. Methods: This paper focuses on the c...

  2. Review of ASME nuclear codes and standards- subcommittee on repairs, replacements, and modifications

    International Nuclear Information System (INIS)

    Mawson, T.J.

    1990-01-01

    As requested by the ASME board on Nuclear Codes and Standards, the Pressure Vessel Research Committee initiated a project to review Sections III and XI of the ASME Boiler and Pressure Vessel Code for the purposes of improving, clarifying, providing transition, consistency, compatibility, and simplifying code requirements. The project was organized with six subcommittees to address various Code activities: design; tests and examinations; documentation; quality assurance; repair, replacement and modification; and general requirements. This paper discusses how the subcommittee on repair, replacement and modification was organized to review the repair, replacement and modification requirements of the ASME boiler and pressure vessel code, Section III and Section XI for Class 1, 2, and 3 and MC components and their supports, and other documents of the nuclear industry related to the repair, replacement and modification requirements of the ASME code

  3. Views on seismic design standardization of structures, systems and components of nuclear facilities

    International Nuclear Information System (INIS)

    Reddy, G.R.

    2011-01-01

    Structures, Systems and Components (SSCs) of nuclear facilities have to be designed for normal operating loads such as dead weight, pressure, temperature etc., and accidental loads such as earthquakes, floods, extreme, wind air craft impact, explosions etc. Manmade accidents such as aircraft impact, explosions etc., sometimes may be considered as design basis event and sometimes taken care by providing administrative controls. This will not be possible in the case of natural events such as earthquakes, flooding, extreme winds etc. Among natural events earthquakes are considered as most devastating and need to be considered as design basis event which has certain annual frequency specified in design codes. For example nuclear power plants are designed for a seismic event has 10000 year return period. It is generally felt that design of SSCs for earthquake loads is very time consuming and expensive. Conventional seismic design approaches demands for large number of supports for systems and components. This results in large space occupation and in turn creates difficulties for maintenance and in service inspection of systems and components. In addition, complete exercise of design need to be repeated for plants being located at different sites due to different seismic demands. However, advanced seismic response control methods will help to standardize the seismic design meeting the safety and economy. These methods adopt passive, semi active and active devices, and base isolators to control the seismic response. In nuclear industry, it is advisable to go for passive devices to control the seismic responses. Ideally speaking, these methods will make the designs made for normal loads can also satisfy the seismic demand without calling for change in material, geometry, layout etc. in the SSCs. This paper explain the basic ideas of seismic response control methods, demonstrate the effectiveness of control methods through case studies and eventually give the procedure to

  4. IEEE standard for design qualification of safety systems equipment used in nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    This standard is written to serve as a general standard for qualification of all types of safety systems equipment, mechanical and instrumentation as well as electrical. It also establishes principles and procedures to be followed in preparing specific safety systems equipment standards. Guidance for qualifying specific safety systems equipment may be found in various specific equipment qualification standards that are now available or are being prepared. It is required that safety systems equipment in nuclear power generating stations meet or exceed its performance requirements throughout its installed life. This is accomplished by a disciplined program of design qualification and quality assurance of design, production, installation, maintenance and surveillance. This standard is for the design qualification section of the program only. Design qualification is intended to demonstrate the capability of the equipment design to perform its safety function(s) over the expected range of normal, abnormal, design basis event, post design basis event, and in-service test conditions. Inherent to design qualification is the requirement for demonstration, within limitations afforded by established technical state-of-the-art, that in-service aging throughout the qualified life established for the equipment will not degrade safety systems equipment from its original design condition to the point where it cannot perform its required safety function(s), upon demand. The above requirement reflects the primary role of design qualification to provide reasonable assurance that design- and age-related common failure modes will not occur during performance of safety function(s) under postulated service conditions

  5. Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel and Transuranic Radioactive Wastes (40 CFR Part 191)

    Science.gov (United States)

    This regulation sets environmental standards for public protection from the management and disposal of spent nuclear fuel, high-level wastes and wastes that contain elements with atomic numbers higher than uranium (transuranic wastes).

  6. IEEE Std 649-1980: IEEE standard for qualifying Class 1E motor control centers for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This standard describes the basic principles, requirements, and methods for qualifying Class 1E motor control centers for outside containment applications in nuclear power generating stations. Qualification of motor control centers located inside containment in a nuclear power generating station is beyond the scope of this standard. The purpose of this standard is (1) to define specific qualification requirements for Class 1E motor control centers in accordance with the more general qualification requirements of IEEE Std 323-1974, IEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations; (2) to provide guidance in establishing a qualification program for demonstrating the design adequacy of Class 1E motor control centers in nuclear power generating station applications

  7. Draft CSA standard on environmental risk assessments at class I nuclear facilities and uranium mines and mills

    International Nuclear Information System (INIS)

    Hart, D.; Garisto, N.; Parker, R.; Kovacs, R.; Thompson, B.

    2012-01-01

    The Canadian Standards Association (CSA) is preparing a draft Standard on environmental risk assessments (ERAs) at Class I nuclear facilities and uranium mines and mills (CSA N288.6). It is being prepared by a technical subcommittee of the CSA N288 Technical Committee, including experts from across the nuclear industry, government and regulatory authorities, and environmental service providers, among others. It addresses the design, implementation, and management of environmental risk assessment programs, and is intended to standardize practice across the industry. This paper outlines the scope of the draft Standard and highlights key features. It is under development and subject to change. (author)

  8. Standard model for the safety analysis report of nuclear fuel reprocessing plants

    International Nuclear Information System (INIS)

    1980-02-01

    This norm establishes the Standard Model for the Safety Analysis Report of Nuclear Fuel Reprocessing Plants, comprehending the presentation format, the detailing level of the minimum information required by the CNEN for evaluation the requests of Construction License or Operation Authorization, in accordance with the legislation in force. This regulation applies to the following basic reports: Preliminary Safety Analysis Report - PSAR, integrating part of the requirement of Construction License; and Final Safety Analysis Report (FSAR) which is the integrating part of the requirement for Operation Authorization

  9. ASTM STANDARD GUIDE FOR EVALUATING DISPOSAL OPTIONS FOR REUSE OF CONCRETE FROM NUCLEAR FACILITY DECOMMISSIONING

    International Nuclear Information System (INIS)

    Phillips, Ann Marie; Meservey, Richard H.

    2003-01-01

    Within the nuclear industry, many contaminated facilities that require decommissioning contain huge volumes of concrete. This concrete is generally disposed of as low-level waste at a high cost. Much of the concrete is lightly contaminated and could be reused as roadbed, fill material, or aggregate for new concrete, thus saving millions of dollars. However, because of the possibility of volumetric contamination and the lack of a method to evaluate the risks and costs of reusing concrete, reuse is rarely considered. To address this problem, Argonne National Laboratory-East (ANL-E) and the Idaho National Engineering and Environmental Laboratory teamed to write a ''concrete protocol'' to help evaluate the ramifications of reusing concrete within the U.S. Department of Energy (DOE). This document, titled the Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Site (1) is based on ANL-E's previously developed scrap metal recycle protocols; on the 10-step method outlined in DOE's draft handbook, Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material (2); and on DOE Order 4500.5, Radiation Protection of the Public and the Environment (3). The DOE concrete protocol was the basis for the ASTM Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning, which was written to make the information available to a wider audience outside DOE. The resulting ASTM Standard Guide is a more concise version that can be used by the nuclear industry worldwide to evaluate the risks and costs of reusing concrete from nuclear facility decommissioning. The bulk of the ASTM Standard Guide focuses on evaluating the dose and cost for each disposal option. The user calculates these from the detailed formulas and tabulated data provided, then compares the dose and cost for each disposal option to select the best option that meets regulatory requirements. With this information

  10. A framework for regulatory requirements and industry standards for new nuclear power plants

    International Nuclear Information System (INIS)

    Duran, Felicia A.; Camp, Allen L.; Apostolakis, George E.; Golay, Michael W.

    2000-01-01

    This paper summarizes the development of a framework for risk-based regulation and design for new nuclear power plants. Probabilistic risk assessment methods and a rationalist approach to defense in depth are used to develop a framework that can be applied to identify systematically the regulations and standards required to maintain the desired level of safety and reliability. By implementing such a framework, it is expected that the resulting body of requirements will provide a regulatory environment that will ensure protection of the public, will eliminate the burden of requirements that do not contribute significantly to safety, and thereby will improve the market competitiveness of new plants. (author)

  11. Effects of Psychiatric Symptoms on Attention in North Korean Refugees.

    Science.gov (United States)

    Lee, Yu Jin; Jun, Jin Yong; Park, Juhyun; Kim, Soohyun; Gwak, Ah Reum; Lee, So Hee; Yoo, So Young; Kim, Seog Ju

    2016-09-01

    We investigated the performance of North Korean refugees on attention tasks, and the relationship between that performance and psychiatric symptoms. Sustained and divided attention was assessed using the computerized Comprehensive Attention Test in North Korean refugees and in South Koreans. All participants also completed the Beck Depression Inventory, the Beck Anxiety Inventory, the Impact of Event Scale-Revised and the Dissociative Experiences Scale-II (DES-II). The North Korean refugees showed slower reaction times (RTs) on the visual sustained attention task compared to the South Koreans after controlling for age and sex. North Korean refugees had a greater number of omission errors (OEs) on the divided attention task and a higher standard deviation (SD) of RT. Total DES-II scores of the North Korean refugees were associated with the number of OEs and the SD of RT on the sustained attention task, and with the number of OEs on the divided attention task. North Korean refugees showed poorer performance on computerized attention tasks. In addition, attention deficit among North Korean refugees was associated with their dissociative experiences. Our results suggest that refugees may have attention deficits, which may be related to their psychiatric symptoms, particularly dissociation.

  12. Solution standards for quality control of nuclear-material analytical measurements

    International Nuclear Information System (INIS)

    Clark, J.P.

    1981-01-01

    Analytical chemistry measurement control depends upon reliable solution standards. At the Savannah River Plant Control Laboratory over a thousand analytical measurements are made daily for process control, product specification, accountability, and nuclear safety. Large quantities of solution standards are required for a measurement quality control program covering the many different analytical chemistry methods. Savannah River Plant produced uranium, plutonium, neptunium, and americium metals or oxides are dissolved to prepare stock solutions for working or Quality Control Standards (QCS). Because extensive analytical effort is required to characterize or confirm these solutions, they are prepared in large quantities. These stock solutions are diluted and blended with different chemicals and/or each other to synthesize QCS that match the matrices of different process streams. The target uncertainty of a standard's reference value is 10% of the limit of error of the methods used for routine measurements. Standard Reference Materials from NBS are used according to special procedures to calibrate the methods used in measuring the uranium and plutonium standards so traceability can be established. Special precautions are required to minimize the effects of temperature, radiolysis, and evaporation. Standard reference values are periodically corrected to eliminate systematic errors caused by evaporation or decay products. Measurement control is achieved by requiring analysts to analyze a blind QCS each shift a measurement system is used on plant samples. Computer evaluation determines whether or not a measurement is within the +- 3 sigma control limits. Monthly evaluations of the QCS measurements are made to determine current bias correction factors for accountability measurements and detect significant changes in the bias and precision statistics. The evaluations are also used to plan activities for improving the reliability of the analytical chemistry measurements

  13. EURATOM work on standard defects and dimensional measurements in neutron radiography of nuclear fuel elements

    International Nuclear Information System (INIS)

    Domanus, J.C.

    1981-10-01

    In 1979 a working group on neutron radiography was formed at Euratom. The purpose of this group is the standardization of neutron radiographic methods in the field of nuclear fuel. First priority was given to the development of image quality indicators and standard objects for the determination of accuracy of dimensional measurements from neutron radiographs. For that purpose beam purity and sensitivity indicators as well as a calibration fuel pin were designed and fabricated at Risoe. All the Euratom neutron radiography centers have recieved the above items for comparative neutron radiography. The measuring results obtained, using various measuring apparatus, will form the basis to formulate conclusions about the best measuring methods and instruments to be used in that field. (author)

  14. Synthesis and applications of 18O standards for nuclear reaction analysis

    Science.gov (United States)

    Pitthan, E.; Corrêa, S. A.; Soares, G. V.; Radtke, C.; Stedile, F. C.

    2014-08-01

    A new method to synthesize 18O standard samples to be used in nuclear reaction analyses is proposed and investigated. This method consists of obtaining a Si18O2 film on a Si substrate using a natural abundance SiO2 film as a passivation layer to prevent the isotopically enriched film to be exposed to the atmosphere and possibly degraded by it. For that, sequential oxidation steps are performed followed by a controlled etching in aqueous hydrofluoric acid. Details of these steps are discussed as well as the stability of the synthesized samples. Applications using these standard samples in the field of alternative semiconductors to Si (SiC and Ge), used in micro and nanoelectronics are also presented.

  15. Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. Volume 2. Radiological health and related standards for nuclear power plants

    International Nuclear Information System (INIS)

    Nero, A.V.; Wong, Y.C.

    1977-01-01

    This report summarizes the status and basis of radiation protection standards, with a view to identifying how they particularly apply to nuclear power plants. The national and international organizations involved in the setting of standards are discussed, paying explicit attention to their jurisdictions and to the considerations they use in setting standards. The routine and accidental radioactive emissions from nuclear power plants are characterized, and the effect of these emissions on ambient radiation levels is discussed. The state of information on the relationship between radiation exposures and health effects is summarized

  16. A common high standard for nuclear power plant exports: overview and analysis of the Nuclear Power Plant Exporters' Principles of Conduct

    International Nuclear Information System (INIS)

    Perkovich, George; Radzinsky, Brian

    2012-01-01

    At this time, there is no overarching global framework to regulate the development of the nuclear power industry. Laws concerning the export of nuclear technology vary across jurisdictions, and politically-binding arrangements such as the Nuclear Suppliers Group (NSG) help ensure that weapons-usable or dual-use technologies are not exported, but no single international regime or agreement manages the gamut of potential risks that may arise from the export of civilian nuclear power plants. Accordingly in 2008, the Carnegie Endowment for International Peace convened internationally-recognised experts in nuclear energy to begin a dialogue with nuclear power plant vendors about defining common criteria for the socially responsible export of nuclear power plants. The goal was to articulate a comprehensive set of principles and best practices that would raise the overall standard of practice for exports of nuclear power plants while enjoying widespread support and adherence. The outcome of this process is the Nuclear Power Plant Exporters' Principles of Conduct - an export-oriented code of conduct for nuclear power plant vendors. The Principles of Conduct help ensure that the participating companies will proceed with the sale of a new nuclear power plant only after a careful assessment of the legal, political, and technical contexts surrounding potential customers. It comprises six 'principles' that each address a major area of concern involved in the export of a nuclear power plant: safety, physical security, environmental protection and spent fuel management, systems of compensation for nuclear damage, non-proliferation and safeguards, and business ethics. The Principles of Conduct entail vendor responsibilities to apply specific standards or engage in certain practices before signing contracts and during the marketing and construction phases of a nuclear power plant export project. Conformity with the Principles of Conduct is voluntary and not-legally binding, but the

  17. Battelle integrity of nuclear piping program. Summary of results and implications for codes/standards

    International Nuclear Information System (INIS)

    Miura, Naoki

    2005-01-01

    The BINP(Battelle Integrity of Nuclear Piping) program was proposed by Battelle to elaborate pipe fracture evaluation methods and to improve LBB and in-service flaw evaluation criteria. The program has been conducted from October 1998 to September 2003. In Japan, CRIEPI participated in the program on behalf of electric utilities and fabricators to catch up the technical backgrounds for possible future revision of LBB and in-service flaw evaluation standards and to investigate the issues needed to be reflected to current domestic standards. A series of the results obtained from the program has been well utilized for the new LBB Regulatory Guide Program by USNRC and for proposal of revised in-service flaw evaluation criteria to the ASME Code Committee. The results were assessed whether they had implications for the existing or future domestic standards. As a result, the impact of many of these issues, which were concerned to be adversely affected to LBB approval or allowable flaw sizes in flaw evaluation criteria, was found to be relatively minor under actual plant conditions. At the same time, some issues that needed to be resolved to address advanced and rational standards in the future were specified. (author)

  18. Research on a methodology for standardization of engineering data in nuclear power plant design

    International Nuclear Information System (INIS)

    Kang, K. D.; Moon, C. K.; Baik, J. H.

    1999-01-01

    The standardization of data and the integration of system are emerging as important issues since each company should handle various kinds of information which is originated from the distributed resources due to rapid development of information technology. Especially for the case of nuclear power plant, the integration of data is very essential since all the data generated during plant lifetime of 40 to 60 years should be maintained and various entities participated in the phase of design, construction and operation of the plant. It is desirable to adopt SGML as a standard in a long-term base for the standardization of NPP engineering data, however there are some difficulties to apply it in current stage. So it is a viable approach to utilize XML as an interim base. In the case of drawings, it is desirable to apply STEP in a long-term base and to apply CAD system in a near term, which can support IGES. Also IGES can be applied in order to store and exchange the drawings. Furthermore, it can be considered to use VRML as a standard for the three dimensional drawings due to the rapid expansion of internet in recent years

  19. Improvements and standardization of communication means for control room personnel in nuclear power plants

    International Nuclear Information System (INIS)

    Preuss, W.; Eggerdinger, C.; Sieber, R.

    1982-01-01

    This report describes the findings of an investigation into selected communication means for control room personnel in nuclear power stations. The study can be seen as a contribution to the systematic analysis of major problem areas which were identified in the general study 'Human factors in the nuclear power plant'. The subjects under investigation were the 'Shift book', 'Simulation book', and 'Technical and organisational changes and their records'. It was intended to analyse both the communication, processes and the associated written documentation in order to determine areas for potential improvement and possibilities for standardization. Information was obtained by interviewing shift members and their supervisors, by general observation, and by compilation and evaluation of the extensive dokumentation. Assessment criteria were developed on a scientific basis and in the course of the investigation, in particular from ergonomic findings, as well as from standards and regulations and comparison between the plants. General practical suggestions were developed for the improvement of the communication forms and the formal design of the documents and their contents. The transfer of the recommendations to practical use in the plants presupposes the consideration of plant-specific frames of reference. The report includes a compilation and listing of suggestions for improvement in topical subdivisions. (orig.) [de

  20. Coupling of standard condensing nuclear power stations to horizontal aluminium tubes multieffect distillation plants

    International Nuclear Information System (INIS)

    Adar, J.

    1977-01-01

    No large nuclear back-pressure turbines are available to-day. Standard condensing nuclear turbines could operate continuously with a back-pressure of up to 7'' Hg, exhausting huge amounts of steam at 56degC-64degC with a loss of electricity production of only 6%-10%. The horizontal aluminium tube multieffect distillation process developed by 'Israel Desalination Engineering Ltd' is very suitable for the use of such low-grade heat. A special flash-chamber loop constitutes a positive barrier against any possible contamination being carried over by the steam exhausted from the turbine to the desalination plant. The operation is designed to be flexible so that the power plant can be operated either in conjunction with the desalination plant or as a single purpose plant. Flow sheets, heat and mass balances have been prepared for eight different combinations of plants. Only standard equipment is being used in the power plant. The desalination plant consists of 6 to 12 parallel double lines, each of them similar to a large prototype now being designed. Water production varies between 50 and 123 MGD and water cost between 90 and 137 c/1000 gallons. Costs are based on actual bids

  1. International safety standards and regulatory practices and their application to Brazilian nuclear power plants - a realistic view

    International Nuclear Information System (INIS)

    Almeida, Claudio; Camargo, Claudio

    1999-01-01

    An international nuclear safety regime is being established through a series of binding safety conventions, voluntarily adopted international safety standards and an accompanying peer review process. The basis for the evaluation of each country performance within this international regime should be the international practices. However, local conditions should be taken into account to avoid undue stress of the limited resources available to countries with a limited nuclear power programme. This work reviews the current international nuclear safety and discusses the application of some international practices to the Brazilian situation, considering the peculiarities of the national nuclear power programme and the limitations of the available financial and human resources. (author)

  2. The evolution of IRRR nuclear standards from the single failure criterion and their impact on system design

    International Nuclear Information System (INIS)

    Clark, D.H.

    1978-01-01

    One of the first industry standards developed in the United States to meet regulatory agency criteria for the design and installation of nuclear power plant control and instrumentation systems was prepared by the Institute of Electrical and Electronics Engineers, Inc., abbreviated IEEE. This was IEEE Std. 279, first issued in 1968. It was subsequently revised and reissued as IEEE Std. 279-1971 ''IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations''. Not only has the implementation of this standard had a tremendous impact on nuclear power plant design in the United States, it has been the base document from which subsequent IEEE nuclear standards have been developed. Three major concepts which are addressed by IEEE 279, and which have had a major impact upon control and instrumentation systems in nuclear power plants are the following : 1) Single failure criterion. 2) Equipment qualification. 3) Channel independence. Each of these concepts has resulted in the development of subsequent IEEE Nuclear Standards. The impact of some of these on control and instrumentation systems are discussed. (author)

  3. The management of electronic documents generated from compilation and revision processes of nuclear and radiation safety regulations and standards

    International Nuclear Information System (INIS)

    Wang Wenhai; Fan Yun; Shang Zhaorong

    2010-01-01

    As the Secretary Group of Regulations and Standards Review Committee on nuclear and radiation safe needs to deal with a large number of electronic documents in course of the regulation and standard review meetings, the article gives a systematical method including electronic document file naming and management as well as procedures of file transfer, storage and usage. (authors)

  4. Differences in safety margins between nuclear and conventional design standards with regards to seismic hazard definition and design criteria

    International Nuclear Information System (INIS)

    Elgohary, M.; Saudy, A.; Orbovic, N.; Dejan, D.

    2006-01-01

    With the surging interest in new build nuclear all over the world and a permanent interest in earthquake resistance of nuclear plants, there is a need to quantify the safety margins in nuclear buildings design in comparison to conventional buildings in order to increase the public confidence in the safety of nuclear power plants. Nuclear (CAN3-N289 series) and conventional (NBCC 2005) seismic standards have different approaches regarding the design of civil structures. The origin of the differences lays in the safety philosophy behind the seismic nuclear and conventional standards. Conventional seismic codes contain the minimal requirement destined primarily to safeguard against major structural failure and loss of life. It doesn't limit damage to a certain acceptable degree or maintain function. Nuclear seismic code requires that structures, systems and components important to safety, withstand the effects of earthquakes. The requirement states that for equipment important to safety, both integrity and functionality should be ascertained. The seismic hazard is generally defined on the basis of the annual probability of exceedence (return period). There is a major difference on the return period and the confidence level for design earthquakes between the conventional and the nuclear seismic standards. The seismic design criteria of conventional structures are based on the use of Force Modification Factors to take into account the energy dissipation by incursion in non-elastic domain and the reserve of strength. The use of such factors to lower intentionally the seismic input is consistent with the safety philosophy of the conventional seismic standard which is the 'non collapse' rather than the integrity and/or the operability of the structures or components. Nuclear seismic standard requires that the structure remain in the elastic domain; energy dissipation by incursion in non-elastic domain is not allowed for design basis earthquake conditions. This is

  5. SU-F-J-100: Standardized Biodistribution Template for Nuclear Medicine Dosimetry Collection and Reporting

    Energy Technology Data Exchange (ETDEWEB)

    Kesner, A [University of Colorado, Anschutz Medical Campus, Aurora, Colorado (United States); Poli, G [International Atomic Energy Agency, Vienna, Vienna (Austria); Beykan, S; Lassman, M [University of Wuerzburg, Wuerzberg, Wuerzberg (Germany)

    2016-06-15

    Purpose: As the field of Nuclear Medicine moves forward with efforts to integrate radiation dosimetry into clinical practice we can identify the challenge posed by the lack of standardized dose calculation methods and protocols. All personalized internal dosimetry is derived by projecting biodistribution measurements into dosimetry calculations. In an effort to standardize organization of data and its reporting, we have developed, as a sequel to the EANM recommendation of “Good Dosimetry Reporting”, a freely available biodistribution template, which can be used to create a common point of reference for dosimetry data. It can be disseminated, interpreted, and used for method development widely across the field. Methods: A generalized biodistribution template was built in a comma delineated format (.csv) to be completed by users performing biodistribution measurements. The template is available for free download. The download site includes instructions and other usage details on the template. Results: This is a new resource developed for the community. It is our hope that users will consider integrating it into their dosimetry operations. Having biodistribution data available and easily accessible for all patients processed is a strategy for organizing large amounts of information. It may enable users to create their own databases that can be analyzed for multiple aspects of dosimetry operations. Furthermore, it enables population data to easily be reprocessed using different dosimetry methodologies. With respect to dosimetry-related research and publications, the biodistribution template can be included as supplementary material, and will allow others in the community to better compare calculations and results achieved. Conclusion: As dosimetry in nuclear medicine become more routinely applied in clinical applications, we, as a field, need to develop the infrastructure for handling large amounts of data. Our organ level biodistribution template can be used as a

  6. Development of Safety Culture Assessment Strategy for Korean NPP

    International Nuclear Information System (INIS)

    Park, Jung Hwan; Kim, Jong Hyun

    2014-01-01

    This paper aims at developing the requirements for a method to evaluate the operational safety culture, evaluating currently available methods based on the requirements, and suggesting a method to evaluate and improve the operational safety culture for Korean nuclear power plants. This paper reviews the widely-used methods to assess safety culture for NPPs and their basis. Then, this paper develops the requirements for the method to evaluate operational safety culture for Korean NPPs. Based on these requirements, Korean Safety Culture Indicators (KSCI) and evaluation measures are also suggested. Finally this paper proposes the guidelines to develop improvements to safety culture from the evaluation results

  7. Development of Safety Culture Assessment Strategy for Korean NPP

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jung Hwan; Kim, Jong Hyun [KEPCO, Ulsan (Korea, Republic of)

    2014-08-15

    This paper aims at developing the requirements for a method to evaluate the operational safety culture, evaluating currently available methods based on the requirements, and suggesting a method to evaluate and improve the operational safety culture for Korean nuclear power plants. This paper reviews the widely-used methods to assess safety culture for NPPs and their basis. Then, this paper develops the requirements for the method to evaluate operational safety culture for Korean NPPs. Based on these requirements, Korean Safety Culture Indicators (KSCI) and evaluation measures are also suggested. Finally this paper proposes the guidelines to develop improvements to safety culture from the evaluation results.

  8. Severe Accident Mitigation by using Core Catcher applicable for Korea standard nuclear power plant

    International Nuclear Information System (INIS)

    Park, Hae Kyun; Kim, Sang Nyung

    2013-01-01

    Nuclear power plants have been designed and operated in order to prevent severe accident because of their risk that contains tremendous radioactive materials that are potentially hazardous. Moreover, the government requested the nuclear industry to implement a severe accident management strategy for existing reactors to mitigate the risk of potential severe accidents. However, Korea standard nuclear power plant(APR-1400 and OPR-1000) are much more vulnerable for severe accident management than that of developed countries. Due to the design feature of reactor cavity in Korea standard nuclear power plant, inequable and serious Molten Core-Concrete Interaction(MCCI) may cause considerable safety problem to the reactor containment liner. At worst, it brings the release of radioactive materials to the environment. This accident applies to the fourth level of defense in depth(IAEA 1996), 'severe accident'. This study proposes and designs the 'slope' to secure reactor containment liner integrity when the corium spreads out from the destroyed reactor vessel to the reactor cavity due to the core melting accident. For this, make the initial corium distribution evenly exploit the 'slope' on the basis of the study of Ex-vessel corium behavior to prevent inequable and serious MCCI, in order to mitigate severe accident. The viscosity has a dominant position in the calculation. According to the result, the spread out distance on the slope is 10.7146841m, considering the rough surface of the concrete(slope) and margin of reactor cavity end(under 11m). Easy to design, production and economic feasibility are the advantage of the designed slope in this study. However, the slope design may unsuitable when the sequences of the accidents did not satisfy the assumptions as mentioned. Despite of those disadvantages, the slope will show a great performance to mitigate the severe accident. As mentioned in assumption, the corium releasing time property was conservatively calculated

  9. Severe Accident Mitigation by using Core Catcher applicable for Korea standard nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hae Kyun; Kim, Sang Nyung [Kyung Hee Univ., Yongin (Korea, Republic of)

    2013-10-15

    Nuclear power plants have been designed and operated in order to prevent severe accident because of their risk that contains tremendous radioactive materials that are potentially hazardous. Moreover, the government requested the nuclear industry to implement a severe accident management strategy for existing reactors to mitigate the risk of potential severe accidents. However, Korea standard nuclear power plant(APR-1400 and OPR-1000) are much more vulnerable for severe accident management than that of developed countries. Due to the design feature of reactor cavity in Korea standard nuclear power plant, inequable and serious Molten Core-Concrete Interaction(MCCI) may cause considerable safety problem to the reactor containment liner. At worst, it brings the release of radioactive materials to the environment. This accident applies to the fourth level of defense in depth(IAEA 1996), 'severe accident'. This study proposes and designs the 'slope' to secure reactor containment liner integrity when the corium spreads out from the destroyed reactor vessel to the reactor cavity due to the core melting accident. For this, make the initial corium distribution evenly exploit the 'slope' on the basis of the study of Ex-vessel corium behavior to prevent inequable and serious MCCI, in order to mitigate severe accident. The viscosity has a dominant position in the calculation. According to the result, the spread out distance on the slope is 10.7146841m, considering the rough surface of the concrete(slope) and margin of reactor cavity end(under 11m). Easy to design, production and economic feasibility are the advantage of the designed slope in this study. However, the slope design may unsuitable when the sequences of the accidents did not satisfy the assumptions as mentioned. Despite of those disadvantages, the slope will show a great performance to mitigate the severe accident. As mentioned in assumption, the corium releasing time property was

  10. A basis for standardized seismic design (SSD) for nuclear power plants/critical facilities

    International Nuclear Information System (INIS)

    O'Hara, T.F.; Jacobson, J.P.; Bellini, F.X.

    1991-01-01

    US Nuclear Power Plants (NPP's) are designed, engineered and constructed to stringent standards. Their seismic adequacy is assured by compliance with regulatory standards and demonstrated by both probabilistic risk assessments (PRAs) and seismic margin studies. However, present seismic siting criteria requires improvement. Proposed changes to siting criteria discussed here will provide a predictable licensing process and a stable regulatory environment. Two recent state-of-the-art studies evaluate the seismic design for all eastern US (EUS) NPP'S: a Lawrence Livermore National Labs study (LLNL, 1989) funded by the NRC and similar research by the Electric Power Research Institute (EPRI, 1989) supported by the utilities. Both confirm that Appendix A 10CFR Part 100 has not provided consistent seismic design levels for all sites. Standardized Seismic Design (SSD) uses a probabilistic framework to accommodate alternative deterministic interpretations. It uses seismic hazard input from EPRI or LLNL to produce consistent bases for future seismic design. SSD combines deterministic and probabilistic insights to provide a comprehensive approach for determining a future site's acceptable seismic design basis

  11. IEEE Std 317-1972: IEEE standard for electric penetration assemblies in containment structures for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    This standard prescribes the mechanical, electrical, and test requirements for the design, construction, and installation of electric penetration assemblies in containment structures for stationary nuclear power generating stations. The electric conductor and insulation characteristics of external circuits which connect to penetration assemblies are beyond the scope of these criteria. If there should be any conflict between this standard and those documents referenced herein, this standard shall take precedence over the referenced documents

  12. A no-gold-standard technique for objective assessment of quantitative nuclear-medicine imaging methods.

    Science.gov (United States)

    Jha, Abhinav K; Caffo, Brian; Frey, Eric C

    2016-04-07

    The objective optimization and evaluation of nuclear-medicine quantitative imaging methods using patient data is highly desirable but often hindered by the lack of a gold standard. Previously, a regression-without-truth (RWT) approach has been proposed for evaluating quantitative imaging methods in the absence of a gold standard, but this approach implicitly assumes that bounds on the distribution of true values are known. Several quantitative imaging methods in nuclear-medicine imaging measure parameters where these bounds are not known, such as the activity concentration in an organ or the volume of a tumor. We extended upon the RWT approach to develop a no-gold-standard (NGS) technique for objectively evaluating such quantitative nuclear-medicine imaging methods with patient data in the absence of any ground truth. Using the parameters estimated with the NGS technique, a figure of merit, the noise-to-slope ratio (NSR), can be computed, which can rank the methods on the basis of precision. An issue with NGS evaluation techniques is the requirement of a large number of patient studies. To reduce this requirement, the proposed method explored the use of multiple quantitative measurements from the same patient, such as the activity concentration values from different organs in the same patient. The proposed technique was evaluated using rigorous numerical experiments and using data from realistic simulation studies. The numerical experiments demonstrated that the NSR was estimated accurately using the proposed NGS technique when the bounds on the distribution of true values were not precisely known, thus serving as a very reliable metric for ranking the methods on the basis of precision. In the realistic simulation study, the NGS technique was used to rank reconstruction methods for quantitative single-photon emission computed tomography (SPECT) based on their performance on the task of estimating the mean activity concentration within a known volume of interest

  13. A no-gold-standard technique for objective assessment of quantitative nuclear-medicine imaging methods

    International Nuclear Information System (INIS)

    Jha, Abhinav K; Frey, Eric C; Caffo, Brian

    2016-01-01

    The objective optimization and evaluation of nuclear-medicine quantitative imaging methods using patient data is highly desirable but often hindered by the lack of a gold standard. Previously, a regression-without-truth (RWT) approach has been proposed for evaluating quantitative imaging methods in the absence of a gold standard, but this approach implicitly assumes that bounds on the distribution of true values are known. Several quantitative imaging methods in nuclear-medicine imaging measure parameters where these bounds are not known, such as the activity concentration in an organ or the volume of a tumor. We extended upon the RWT approach to develop a no-gold-standard (NGS) technique for objectively evaluating such quantitative nuclear-medicine imaging methods with patient data in the absence of any ground truth. Using the parameters estimated with the NGS technique, a figure of merit, the noise-to-slope ratio (NSR), can be computed, which can rank the methods on the basis of precision. An issue with NGS evaluation techniques is the requirement of a large number of patient studies. To reduce this requirement, the proposed method explored the use of multiple quantitative measurements from the same patient, such as the activity concentration values from different organs in the same patient. The proposed technique was evaluated using rigorous numerical experiments and using data from realistic simulation studies. The numerical experiments demonstrated that the NSR was estimated accurately using the proposed NGS technique when the bounds on the distribution of true values were not precisely known, thus serving as a very reliable metric for ranking the methods on the basis of precision. In the realistic simulation study, the NGS technique was used to rank reconstruction methods for quantitative single-photon emission computed tomography (SPECT) based on their performance on the task of estimating the mean activity concentration within a known volume of interest

  14. Los Alamos National Laboratory new generation standard nuclear material storage container - the SAVY4000 design

    International Nuclear Information System (INIS)

    Stone, Timothy Amos

    2010-01-01

    Incidents involving release of nuclear materials stored in containers of convenience such as food pack cans, slip lid taped cans, paint cans, etc. has resulted in defense board concerns over the lack of prescriptive performance requirements for interim storage of nuclear materials. Los Alamos National Laboratory (LANL) has shared in these incidents and in response proactively moved into developing a performance based standard involving storage of nuclear material (RD003). This RD003 requirements document has sense been updated to reflect requirements as identified with recently issued DOE M 441.1-1 'Nuclear Material Packaging Manual'. The new packaging manual was issued at the encouragement of the Defense Nuclear Facilities Safety Board with a clear directive for protecting the worker from exposure due to loss of containment of stored materials. The Manual specifies a detailed and all inclusive approach to achieve a high level of protection; from package design and performance requirements, design life determinations of limited life components, authorized contents evaluations, and surveillance/maintenance to ensure in use package integrity over time. Materials in scope involve those stored outside an approved engineered-contamination barrier that would result in a worker exposure of in excess of 5 rem Committed Effective Does Equivalent (CEDE). Key aspects of meeting the challenge as developed around the SAVY-3000 vented storage container design will be discussed. Design performance and acceptance criteria against the manual, bounding conditions as established that the user must ensure are met to authorize contents in the package (based upon the activity of heat-source plutonium (90% Pu-238) oxide, which bounds the requirements for weapons-grade plutonium oxide), interface as a safety class system within the facility under the LANL plutonium facility DSA, design life determinations for limited life components, and a sense of design specific surveillance program

  15. Differences in Approach between Nuclear and Conventional Seismic Standards with regard to Hazard Definition - CSNI Integrity And Ageing Working Group

    International Nuclear Information System (INIS)

    Djaoudi, Ali; Labbe, Pierre; Murphy, Andrew; Kitada, Yoshio

    2008-01-01

    The Committee on the safety of Nuclear Installations (CSNI) of the OECD-NEA co-ordinates the NEA activities related to maintaining and advancing the scientific and technological knowledge base of the safety of nuclear installations. The Integrity and Ageing of Components and Structures Working Group of the CSNI is responsible for work related to the development and use of methods, data and information to assess the behaviour of materials and structures. It has three sub-groups, dealing with the integrity of metal components and structures, ageing of concrete structures, and the seismic behaviour of structures. The CSNI, at its meeting in June 2003, agreed to initiate an activity aimed to identify any difference between nuclear and non-nuclear conventional standards and their potential significance with regard to seismic hazards and design methods. There was a perception, mainly in some of the European countries that nuclear seismic hazard and design standards may be lagging behind developments in similar standards for conventional facilities. Adequate answer to such perception, need the examination of the following aspects and their significance on the seismic assessment of structures and components: - The safety philosophy behind the seismic nuclear and conventional standards. - The differences in approach regarding the seismic hazard definition. - The difference in approach regarding the design and the methods of analysis. These topics are examined in this report. Appendices A to H of this report contain a brief description of the conventional and the nuclear approaches in the NEA member countries: Belgium, Canada, Czech Republic, Germany, Japan, South Korea, Spain,and USA. The following general conclusions can be drawn: - The approach adopted by the nuclear seismic standards is more conservative and more reliable (in particular for meeting the continued operation criteria) than the recommended by the currently applicable force based conventional seismic codes

  16. Management of immune thrombocytopenia: Korean experts recommendation in 2017.

    Science.gov (United States)

    Jang, Jun Ho; Kim, Ji Yoon; Mun, Yeung-Chul; Bang, Soo-Mee; Lim, Yeon Jung; Shin, Dong-Yeop; Choi, Young Bae; Yhim, Ho-Young; Lee, Jong Wook; Kook, Hoon

    2017-12-01

    Management options for patients with immune thrombocytopenia (ITP) have evolved substantially over the past decades. The American Society of Hematology published a treatment guideline for clinicians referring to the management of ITP in 2011. This evidence-based practice guideline for ITP enables the appropriate treatment of a larger proportion of patients and the maintenance of normal platelet counts. Korean authority operates a unified mandatory national health insurance system. Even though we have a uniform standard guideline enforced by insurance reimbursement, there are several unsolved issues in real practice in ITP treatment. To optimize the management of Korean ITP patients, the Korean Society of Hematology Aplastic Anemia Working Party (KSHAAWP) reviewed the consensus and the Korean data on the clinical practices of ITP therapy. Here, we report a Korean expert recommendation guide for the management of ITP.

  17. Evaluation of advanced containment features proposed to Korean SNPP

    International Nuclear Information System (INIS)

    Jin, Y.; Park, S.Y.; Kim, S.D.; Kim, D.H.

    1997-01-01

    Korean Standard Nuclear Power Plant (KSNP) has adopted many advanced design features to enhance its containment performance during severe accidents as well as to reduce changes of core damage. Robust design of containment and hydrogen mixing capability reduced containment failure probability significantly. In addition to these features, new systems are proposed for KSNP: advanced design of cavity geometry, reactor cavity flooding system, hydrogen igniter, and containment filtered venting system. Before these proposals are adopted to the KSNP, their effectiveness on containment performance has been assessed systematically. Containment event tree and sensitivity analysis are used to quantify the effectiveness of these design features. The overall results indicate that these new features do not improve the containment performance significantly except the containment filtered venting system. But adoption of the containment filtered venting system should be examined carefully because accidental failure of this system may result in undue risk to public. (author)

  18. Cernavoda nuclear power plant: Modifications in the fire protection measures of the CANDU 6 standard design

    International Nuclear Information System (INIS)

    Covalschi, V.

    1998-01-01

    Having as purpose the improvement of fire safety at the Cernavoda NPP - both in the prevention and the protection aspects in the case of fire - we implemented some modifications in the CANDU 6 standard design. These improvements are inspired, mainly, from two sources: the world-wide achievements in the field of fire protection techniques, introduced in nuclear power plants since the middle of 70's, when the CANDU 6 design was completed; the national practice and experience in fire protection, usually applied in industrial objectives (conventional power plants, in particular). The absence of any incident may be considered as a proof of the efficiency of the implemented fire preventing and protection measures. (author)

  19. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2011-01-01

    1.1 These test methods cover procedures for subsampling and for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride UF6. Most of these test methods are in routine use to determine conformance to UF6 specifications in the Enrichment and Conversion Facilities. 1.2 The analytical procedures in this document appear in the following order: Note 1—Subcommittee C26.05 will confer with C26.02 concerning the renumbered section in Test Methods C761 to determine how concerns with renumbering these sections, as analytical methods are replaced with stand-alone analytical methods, are best addressed in subsequent publications. Sections Subsampling of Uranium Hexafluoride 7 - 10 Gravimetric Determination of Uranium 11 - 19 Titrimetric Determination of Uranium 20 Preparation of High-Purity U3O 8 21 Isotopic Analysis 22 Isotopic Analysis by Double-Standard Mass-Spectrometer Method 23 - 29 Determination of Hydrocarbons, Chlorocarbons, and Partially Substitut...

  20. Development of alarm cause tracking system for Korea standard nuclear power plant

    International Nuclear Information System (INIS)

    Lee, Jung Woon; Kim, Jung Taek; Park, Jae Chang; Lee, Hyun Chul; Park, Joong Pal

    2004-05-01

    The proposed system, the ACTS(Alarm Cause Tracking System), in the 1st and 2nd development period(2001. 7 ∼ 2003. 6), tracks and displays the causes of alarms on-line from computerized logic diagrams. And the system highlights the specific procedures related the causes in the procedure of the alarm. In this period(2003. 7 ∼ 2004. 4), we developed the ACTS for Korea standard nuclear power plant. Also, we computerized control logic diagrams and alarm procedures for the ACTS. A long-term target is to apply the ACTS at the real power plant, and a short-term target is to connect the ACTS with the ITF(Intergrated Test Facility) in KAERI site to develop other applications

  1. Standard Review Plan for the review of safety analysis reports for nuclear power plants: LWR edition

    International Nuclear Information System (INIS)

    1987-06-01

    The Standard Review Plan (SRP) is prepared for the guidance of staff reviewers in the Office of Nuclear Reactor Regulation in performing safety reviews of applications to construct or operate nuclear power plants. The principal purpose of the SRP is to assure the quality and uniformity of staff reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. It is also a purpose of the SRP to make information about regulatory matters widely available and to improve communication and understanding of the staff review process by interested members of the public and the nuclear power industry. The safety review is primarily based on the information provided by an applicant in a Safety Analysis Report (SAR). The SAR must be sufficiently detailed to permit the staff to determine whether the plant can be built and operated without undue risk to the health and safety of the public. The SAR is the principal document in which the applicant provides the information needed to understand the basis upon which this conclusion has been reached. The individual SRP sections address, in detail, who performs the review, the matters that are reviewed, the basis for review, how the review is accomplished, and the conclusions that are sought. The safety review is performed by 25 primary branches. One of the objectives of the SRP is to assign the review responsibilities to the various branches and to define the sometimes complex interfaces between them. Each SRP section identifies the branch that has the primary review responsibility for that section. In some review areas the primary branch may require support, and the branches that are assigned these secondary review responsibilities are also identified for each SRP section

  2. French codes and standards for design, construction and in-service inspection of nuclear power plants

    International Nuclear Information System (INIS)

    Hugot, G.; Grandemange, J. M.

    1995-01-01

    In 1970, France decided that its future power plants would be of the Pressurized Water Reactor type. This choice proved to be successful since it resulted in more than 60 PWR units in operation or under construction in France and abroad. At the beginning of such a program, the French engineering and manufacturing industry, the national electrical utility and the Safety Authorities had to face the many challenges imposed by the implementation of an imported technology. The government reorganised the licensing process. FRAMATOME, the NSSS vendor, and EDF (Electricite de France), the national utility, decided to create 'AFCEN', the French Association for Design and Construction Rules for Nuclear Island Components. These rules, the RCC's (Regles de Construction et de conception), which are approved by French Safety Authorities deal with mechanical and electrical equipment as well as with nuclear fuel and civil works. They are now being supplemented by in service inspection rules, the RSE's (Regles d'inspection en Service). The paper presents these Codes and their main updating following experience of application, technical progress and evolution of standards. Status of discussion concerning reference to European standardisation and developments of rules applicable to the EPR project will also be discussed

  3. Korean Screen Cultures

    DEFF Research Database (Denmark)

    Screen Cultures sets out to redress this imbalance with a broad selection of essays spanning both North and South as well as different methodological approaches, from ethnographic and audience studies to cultural materialist readings. The first section of the book, «The South», highlights popular media...... new approaches to Korean popular culture beyond national borders and includes work on K-pop and Korean television drama. This book is a vital addition to existing scholarship on Korean popular culture, offering a unique view by providing an imaginary unification of the two Koreas negotiated through...

  4. Understanding Korean food culture from Korean paintings

    Directory of Open Access Journals (Sweden)

    Hae Kyung Chung

    2016-03-01

    Conclusion: Beyond the basic value of food in maximizing nutrients and energy, Korean food culture has developed distinctive cultural characteristics through more than 5,000 years of agricultural history. Although the genre paintings analyzed in this paper are limited to a certain era, this paper will serve as a milestone in providing direction for future studies.

  5. Design reliability assurance program for Korean next generation reactor

    International Nuclear Information System (INIS)

    Lee, Beom-Su; Han, Jin-Kyu; Na, Jang Hwan; Yoo, Kyung Yeong

    1997-01-01

    The Korean Next Generation Reactor (KNGR) project is to develop standardized nuclear power plant design for the construction of future nuclear power plants in Korea. The main purpose of the KNGR project is to develop the advanced nuclear power plants, which enhance safety and economics significantly through the incorporation of design concepts for severe accident prevention and mitigation, supplementary passive safety concept, simplification and application of modularization and so on. For those, Probabilistic Safety Assessment (PSA) and availability study will be performed at the early stage of the design, and the Design Reliability Assurance Program (D-RAP) is applied in the development of the KNGR to ensure that the safety and availability evaluated in the PSA and availability study at the early phase of the design is maintained through the detailed design, construction, procurement and operation of the plants. This paper presents the D-RAP concept that could be applied at the stage of the basic design of the nuclear power plants, based on the models for the reference plants and/or similar plants. 4 refs., 1 fig

  6. Problems and solutions in application of IEEE standards at Savannah River Site, Department of Energy (DOE) nuclear facilities

    International Nuclear Information System (INIS)

    Lee, Y.S.; Bowers, T.L.; Chopra, B.J.; Thompson, T.T.; Zimmerman, E.W.

    1993-01-01

    The Department of Energy (DOE) Nuclear Material Production Facilities at the Savannah River Site (SRS) were designed, constructed, and placed into operation in the early 1950's, based on existing industry codes/standards, design criteria, analytical procedures. Since that time, DOE has developed Orders and Polices for the planning, design and construction of DOE Nuclear Reactor Facilities which invoke or reference commercial nuclear reactor codes and standards. The application of IEEE reactor design requirements such as Equipment Qualification, Seismic Qualification, Single Failure Criteria, and Separation Requirement, to non-reactor facilities has been a problem since the IEEE reactor criteria do not directly confirm to the needs of non-reactor facilities. SRS Systems Engineering is developing a methodology for the application of IEEE Standards to non-reactor facilities at SRS

  7. IEEE standard requirements for reliability analysis in the design and operation of safety systems for nuclear power generating stations

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The purpose of this standard is to provide uniform, minimum acceptable requirements for the performance of reliability analyses for safety-related systems found in nuclear-power generating stations, but not to define the need for an analysis. The need for reliability analysis has been identified in other standards which expand the requirements of regulations (e.g., IEEE Std 379-1972 (ANSI N41.2-1972), ''Guide for the Application of the Single-Failure Criterion to Nuclear Power Generating Station Protection System,'' which describes the application of the single-failure criterion). IEEE Std 352-1975, ''Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Protection Systems,'' provides guidance in the application and use of reliability techniques referred to in this standard

  8. Testing of adsorbents used in nuclear power plant air cleaning systems using the open-quotes Newclose quotes standards

    International Nuclear Information System (INIS)

    Freeman, W.P.

    1993-01-01

    Ever since the publication of the NRC Information Notice No. 87-32: Deficiencies in the Testing of Nuclear-Grade Activated Charcoal, nuclear power facilities in the US have struggled in their efforts to open-quotes...review the information for applicability to their facilities and consider action, if appropriate ...close quotes as stated in the notice. The encouragement of resident NRC inspectors at some nuclear power facilities has prompted a variety of responses ranging from no change at all in testing requirements to contemplated changes in plant technical specifications. This confusion is the result of a couple factors. The first factor is the lack of a current revision to NRC Regulatory Guide 1.52, the basic document used in nuclear power plant technical specifications for the testing of engineered-safety feature (ESF) post accident air cleaning systems. The second factor is the standards that have been written since the last revision of Reg. Guide 1.52 which include two revision of ANSI N509 and N510, two revisions of RDT M16-1T, two version of ASTM D3803, two versions of ASTM D4069, and three versions of an SME code AG-1. Few of the standards and codes listed above are commensurate with each other and, thus, present a nearly insolvable maze to the HVAC engineer asked to upgrade adsorbent testing requirements following the standards. This paper describes the authors experience with a number of nuclear power facilities in their efforts to meet the requirements of the new standards of testing adsorbents from nuclear power plant air cleaning systems. The existing standards are discussed in light of the current state of the art for adsorbent testing of adsorbent media from nuclear air treatment systems. Test results are presented showing the impact of new test requirements on acceptance criteria when compared to the old test requirements and recommendations are offered for solution of this testing problem in the future. 12 refs., 5 tabs

  9. Standard practice for sampling special nuclear materials in multi-container lots

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1987-01-01

    1.1 This practice provides an aid in designing a sampling and analysis plan for the purpose of minimizing random error in the measurement of the amount of nuclear material in a lot consisting of several containers. The problem addressed is the selection of the number of containers to be sampled, the number of samples to be taken from each sampled container, and the number of aliquot analyses to be performed on each sample. 1.2 This practice provides examples for application as well as the necessary development for understanding the statistics involved. The uniqueness of most situations does not allow presentation of step-by-step procedures for designing sampling plans. It is recommended that a statistician experienced in materials sampling be consulted when developing such plans. 1.3 The values stated in SI units are to be regarded as the standard. 1.4 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standar...

  10. Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2002-01-01

    1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists. 1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1) from ...

  11. Standards for digital computers used in non-safety nuclear power plant applications: objectives and limitations

    International Nuclear Information System (INIS)

    Rorer, D.C.; Long, A.B.

    1977-01-01

    There are currently a number of efforts to develop standards which would apply to digital computers used in nuclear power plants for functions other than those directly involving plant protection (for example, ANS: 4.3.3 Subworking Group in the U.S., IEC 45A/WGA1 Subcommittee in Europe). The impetus for this activity is discussed and generally attributed to the realization that nonsafety systems computers may affect the assumptions used as the design bases for safety systems, the sizable economic loss which can result from the failure of a critical computer application, and the lingering concern about the misapplication of a still-new technology. At the same time, it is pointed out that these standards may create additional obstacles for the use of this new technology which are not present in the application of more conventional instrumentation and control equipment. Much of the U.S. effort has been directed toward the problem of validation of computer systems in which the potential exists for unplanned interactions between various functions in a multiprogram environment, using common hardware in a time-sharing mode. The goal is to develop procedures for the specification, development implementation, and documentation of testable, modular systems which, in the absence of proven quantitative techniques for assessing software reliability, are felt to provide reasonable assurance that the computer system will function as planned

  12. Nuclear power of Korea

    International Nuclear Information System (INIS)

    Chun Bee-Ho

    2011-01-01

    National nuclear is presented. Nuclear energy safety after Fukushima, international cooperation in nuclear energy is discussed. Nuclear projects with the United Arab Emirates have been developed to build 4 nuclear power plants in the UAE - APR 1400. At the Korea-Bulgaria Industrial Committee Meeting in Sofia (March 2011) Korean side proposed Nuclear Safety Training Program in Korea for Bulgarian government officials and experts transfer of know-how and profound expertise on world-class nuclear technology and nuclear safety

  13. Comparative study of Malaysian and Philippine regulatory infrastructures on radiation and nuclear safety with international standards

    International Nuclear Information System (INIS)

    Cayabo, Lynette B.

    2013-06-01

    This study presents the results of the critical reviews, analysis, and comparison of the regulatory infrastructures for radiation and nuclear safety of Malaysis and the Philippines usi ng the IAEA safety requirements, GSR Part 1, G overnment, Legal and Regulatory Framework for Safety'' as the main basis and in part, the GSR Part 3, R adiation Protection and Safety of Radiation Sources: International Basic Safety Standards . The scope of the comparison includes the elements of the relevant legislations, the regulatory system and processes including the core functions of the regulatory body (authorization, review and assessment, inspection and enforcement, development of regulations and guides); and the staffing and training of regulatory body. The respective availabe data of the Malaysian and Philippine regulatory infrastructures and current practices were gathered and analyzed. Recommendations to fill the gaps and strengthen the existing regulatory infrastructure of each country was given using as bases relevant IAEA safety guides. Based on the analysis made, the main findings are: the legislations of both countries do not contain al the elements of teh national policy and strategy for safety as well as those of teh framework for safety in GR Part I. Among the provision that need to be included in the legislations are: emergency planning and response; decommissioning of facilities safe management of radioactive wastes and spent fuel; competence for safety; and technical sevices. Provisions on coordination of different authorities with safety responsibilities within the regulatory framework for safety as well as liaison with advisory bodies and support organizations need to be enhanced. The Philippines needs to establish an independent regulatory body, ie. separate from organizations charged with promotion of nuclear technologies and responsible for facilitiesand activities. Graded approach on the system of notification and authorization by registration and

  14. Korean Affairs Report

    Science.gov (United States)

    1985-09-20

    Pyongyang station, the South Korean delegation boarded 16 Mercedes Benz sedans and seven buses, then headed for the Koryo Hotel. The South Korean...money-making, loudly advertising "relief of hungry children, "relief of the destitute" and "programme for the rebirth of narcotic addicts. It was with... market are twin pains these days. When they convert what they earned on the bearish stock exchange into dol- lars, their returns show minus gains

  15. On Being There: Korean in Japan.

    Science.gov (United States)

    Maher, John C.; Kawanishi, Yumiko

    1995-01-01

    Examines the experiences of ethnic Koreans and the Korean language in Japan since 1945, focusing on Japanese attitudes toward Koreans and the Korean language, provisions for Korean and bilingual education, and the increasing influence of Koreans in Japanese society. (18 references) (MDM)

  16. Application of objective provision tree to development of standard review plan for sodium-cooled fast reactor nuclear design

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Moo-Hoon; Suh, Namduk; Choi, Yongwon; Shin, Andong [Korea Institute of Nuclear Safety, Daejon (Korea, Republic of)

    2016-06-15

    A systematic methodology was developed for the standard review plan for sodium-cooled fast reactor nuclear design. The process is first to develop an objective provision tree of sodium-cooled fast reactor for the reactivity control safety function. The provision tree is generally developed by designer to confirm whether the design satisfies the defense-in-depth concept. Then applicability of the current standard review plan of nuclear design for light water reactor to sodium-cooled fast reactor was evaluated and complemented by the developed objective provision tree.

  17. A real-time computer simulation of nuclear simulator software using standard PC hardware and linux environments

    International Nuclear Information System (INIS)

    Cha, K. H.; Kweon, K. C.

    2001-01-01

    A feasibility study, which standard PC hardware and Real-Time Linux are applied to real-time computer simulation of software for a nuclear simulator, is presented in this paper. The feasibility prototype was established with the existing software in the Compact Nuclear Simulator (CNS). Throughout the real-time implementation in the feasibility prototype, we has identified that the approach can enable the computer-based predictive simulation to be approached, due to both the remarkable improvement in real-time performance and the less efforts for real-time implementation under standard PC hardware and Real-Time Linux envrionments

  18. Review of the Commission program for standardization of nuclear power plants and recommendations to improve standardization concepts

    International Nuclear Information System (INIS)

    1978-02-01

    This is a report of a staff study describing the need and utility of specific changes to the Commission's standardization program. The various matters considered in the study include: (1) A discussion of industry use to date of the standardization program. (2) A discussion of the experience to date with each of the standardization concepts. (3) A review of public comments on the standardization program and the staff response to each principal comment. (4) A review of the need for standardization considering the likely number of license applications to be submitted in the coming years. (5) A discussion of the reference system concept, including review of applicable experience and recommended changes to the concept. (6) A discussion of the duplicate plant concept, including review of applicable experience and recommended changes to the concept. (7) A discussion of the manufacturing license concept, including review of applicable experience and recommended changes to the concept. (8) A discussion of the replicate plant concept, including review of applicable experience and recommended changes to the concept. (9) A discussion of the effective periods for approved designs under all four standardization concepts. (10) A description of continuing staff activities related to the standardization program

  19. A feasibility study on the longer cycle operation of Yonggwang nuclear power plants 3 and 4 (3 rd quarter report)

    Energy Technology Data Exchange (ETDEWEB)

    Zee Sung Kyun; Song, Jae Woong; Ha, Young Joon; Kim, Kyu Tae [Korea Advanced Institute of Science and Technolgoy, Taejon (Korea, Republic of)

    1996-04-01

    In this report, described are results of the feasibility study on applying for the 18-month cycle in Korean Standard Nuclear Power Plants (KSNPs). This report contains results of safety and economic evaluations, radiation source analysis, an effect on changing the calibration period for each component of NSSS, and review on the related regulating codes. 12 refs., 34 tabs., 28 figs. (author)

  20. Promoting safety in nuclear installations. The IAEA has established safety standards for nuclear reactors and provides expert review and safety services to assist Member States in their application

    International Nuclear Information System (INIS)

    2002-01-01

    More than 430 nuclear power plants (NPPs) are currently operating in 30 countries around the world. The nuclear share of total electricity production ranges from about 20 percent in the Czech Republic and United States to nearly 78 percent in France and Lithuania. Worldwide, nuclear power generates about 16% of the total electricity. The safety of such nuclear installations is fundamental. Every aspect of a power plant must be closely supervised and scrutinized by national regulatory bodies to ensure safety at every phase. These aspects include design, construction, commissioning, trial operation, commercial operation, repair and maintenance, plant upgrades, radiation doses to workers, radioactive waste management and, ultimately, plant